Dataset statistics
Number of variables | 12 |
---|---|
Number of observations | 335 |
Missing cells | 0 |
Missing cells (%) | 0.0% |
Duplicate rows | 0 |
Duplicate rows (%) | 0.0% |
Total size in memory | 31.5 KiB |
Average record size in memory | 96.4 B |
Variable types
Text | 5 |
---|---|
Categorical | 7 |
Dataset
Description | 국내 원자력관련 최신동향 발표자료 목록 데이터 입니다. 데이터 칼럼 리스트는 저자, 제목, 출처, 출신지, 페이지, 언어, 소속, 출처, 개최지, 일시, 키워드, 초록 입니다. (연구자가 과학기술분야의 최신 정보를 최단시간에 입수하기 위해서는 가장 적합한 매체는 회의자료이므로 국내에서 개최된 원자력관련 회의 (한국원자력학회, 한국방사성폐기물학회, 한국기계학회 등의 춘추계 학술발표회 및 한국방사선동위원소, 전자빔응용 워크샾 등)와 2개 이상 국가가 참여한 국제회의(한국원자력협회-일본원자력협회의 원자력산업 세미나, 레이저분광학 국제심포지엄 등)가 있으며 주로 발표한 논문, 프레젠테이션 형태의 자료들의 목록) |
---|---|
URL | https://www.data.go.kr/data/3077573/fileData.do |
언어 has constant value "" | Constant |
개최지 is highly overall correlated with 출처 and 4 other fields | High correlation |
학회 is highly overall correlated with 출처 and 4 other fields | High correlation |
일시 is highly overall correlated with 출처 and 4 other fields | High correlation |
출처 is highly overall correlated with 출신지 and 4 other fields | High correlation |
소속 is highly overall correlated with 출처 and 4 other fields | High correlation |
출신지 is highly overall correlated with 출처 and 4 other fields | High correlation |
개최지 is highly imbalanced (94.7%) | Imbalance |
제목 has unique values | Unique |
키워드 has unique values | Unique |
초록 has unique values | Unique |
Reproduction
Analysis started | 2023-12-12 20:08:33.777373 |
---|---|
Analysis finished | 2023-12-12 20:08:34.841619 |
Duration | 1.06 second |
Software version | ydata-profiling vv4.5.1 |
Download configuration | config.json |
저자
Text
Distinct | 327 |
---|---|
Distinct (%) | 97.6% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Length
Max length | 353 |
---|---|
Median length | 182 |
Mean length | 128.95821 |
Min length | 53 |
Characters and Unicode
Total characters | 43201 |
---|---|
Distinct characters | 60 |
Distinct categories | 7 ? |
Distinct scripts | 2 ? |
Distinct blocks | 1 ? |
Unique
Unique | 319 ? |
---|---|
Unique (%) | 95.2% |
Sample
1st row | Lee, Chae Chang (Korea Institute of Nuclear Nonproliferation and Control, Daejeon (KR)) |
---|---|
2nd row | Won, Byung Hee; Park, Se Hwan; Shin, Hee Sung; Ahn, Seong Kyu (Korea Atomic Energy Research Institute, Daejeon (KR)) |
3rd row | Lee, Dong Hyun; Lee, Man Ki; Kim, Hee Reyoung; Min, Byung Joo (Ulsan National Institute of Science and Technology, Ulsan (KR)) |
4th row | Park, Se Hwan; Kim, Ho Dong; Lee, Chae Hoon; Song, Dae Yong; Won, Byung Hee; Ahn, Seong Kyu (Korea Atomic Energy Research Institute, Daejeon (KR)); (Chonbuk National University, Jeonju (KR)) |
5th row | Lee, Sung Ho; Kim, In Chul; Lee, Byung Doo; Kim, Hyun Jo; Kim, Hyun Sook; Jung, Juang (Korea Atomic Energy Research Institute, Daejeon (KR)) |
Value | Count | Frequency (%) |
kr | 404 | 5.8% |
kim | 284 | 4.1% |
institute | 270 | 3.9% |
daejeon | 255 | 3.7% |
korea | 240 | 3.5% |
lee | 217 | 3.1% |
research | 200 | 2.9% |
energy | 167 | 2.4% |
atomic | 166 | 2.4% |
park | 120 | 1.7% |
Other values (723) | 4620 |
Most occurring characters
Value | Count | Frequency (%) |
6610 | 15.3% | |
e | 3542 | 8.2% |
n | 3389 | 7.8% |
o | 2838 | 6.6% |
a | 2180 | 5.0% |
, | 1811 | 4.2% |
i | 1681 | 3.9% |
u | 1394 | 3.2% |
t | 1346 | 3.1% |
g | 1337 | 3.1% |
Other values (50) | 17073 |
Most occurring categories
Value | Count | Frequency (%) |
Lowercase Letter | 24661 | |
Uppercase Letter | 7129 | 16.5% |
Space Separator | 6610 | 15.3% |
Other Punctuation | 3088 | 7.1% |
Close Punctuation | 844 | 2.0% |
Open Punctuation | 844 | 2.0% |
Dash Punctuation | 25 | 0.1% |
Most frequent character per category
Lowercase Letter
Value | Count | Frequency (%) |
e | 3542 | |
n | 3389 | |
o | 2838 | |
a | 2180 | |
i | 1681 | 6.8% |
u | 1394 | 5.7% |
t | 1346 | 5.5% |
g | 1337 | 5.4% |
r | 1139 | 4.6% |
h | 797 | 3.2% |
Other values (16) | 5018 |
Uppercase Letter
Value | Count | Frequency (%) |
K | 1231 | |
R | 662 | 9.3% |
S | 648 | 9.1% |
H | 563 | 7.9% |
J | 483 | 6.8% |
D | 429 | 6.0% |
C | 372 | 5.2% |
I | 361 | 5.1% |
Y | 283 | 4.0% |
L | 281 | 3.9% |
Other values (16) | 1816 |
Other Punctuation
Value | Count | Frequency (%) |
, | 1811 | |
; | 1023 | |
. | 248 | 8.0% |
# | 6 | 0.2% |
Space Separator
Value | Count | Frequency (%) |
6610 |
Close Punctuation
Value | Count | Frequency (%) |
) | 844 |
Open Punctuation
Value | Count | Frequency (%) |
( | 844 |
Dash Punctuation
Value | Count | Frequency (%) |
- | 25 |
Most occurring scripts
Value | Count | Frequency (%) |
Latin | 31790 | |
Common | 11411 | 26.4% |
Most frequent character per script
Latin
Value | Count | Frequency (%) |
e | 3542 | 11.1% |
n | 3389 | 10.7% |
o | 2838 | 8.9% |
a | 2180 | 6.9% |
i | 1681 | 5.3% |
u | 1394 | 4.4% |
t | 1346 | 4.2% |
g | 1337 | 4.2% |
K | 1231 | 3.9% |
r | 1139 | 3.6% |
Other values (42) | 11713 |
Common
Value | Count | Frequency (%) |
6610 | ||
, | 1811 | 15.9% |
; | 1023 | 9.0% |
) | 844 | 7.4% |
( | 844 | 7.4% |
. | 248 | 2.2% |
- | 25 | 0.2% |
# | 6 | 0.1% |
Most occurring blocks
Value | Count | Frequency (%) |
ASCII | 43201 |
Most frequent character per block
ASCII
Value | Count | Frequency (%) |
6610 | 15.3% | |
e | 3542 | 8.2% |
n | 3389 | 7.8% |
o | 2838 | 6.6% |
a | 2180 | 5.0% |
, | 1811 | 4.2% |
i | 1681 | 3.9% |
u | 1394 | 3.2% |
t | 1346 | 3.1% |
g | 1337 | 3.1% |
Other values (50) | 17073 |
제목
Text
UNIQUE
 
Distinct | 335 |
---|---|
Distinct (%) | 100.0% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Length
Max length | 174 |
---|---|
Median length | 122 |
Mean length | 91.334328 |
Min length | 29 |
Characters and Unicode
Total characters | 30597 |
---|---|
Distinct characters | 77 |
Distinct categories | 10 ? |
Distinct scripts | 2 ? |
Distinct blocks | 1 ? |
Unique
Unique | 335 ? |
---|---|
Unique (%) | 100.0% |
Sample
1st row | Review of the US cyber security self-assessment method from the regulatory perspective |
---|---|
2nd row | Algorithm development for detecting a crane on surveillance camera in pyroprocessing based on machine learning technique |
3rd row | Current status of management of human resource for enhancement of radiation safety |
4th row | Development of safeguards approach of intermediate-sized pyroprocessing facility |
5th row | A study on the safeguards of nuclear facility during whole-life |
Value | Count | Frequency (%) |
of | 360 | 8.4% |
for | 153 | 3.6% |
the | 112 | 2.6% |
on | 95 | 2.2% |
and | 88 | 2.1% |
in | 79 | 1.8% |
nuclear | 63 | 1.5% |
fuel | 58 | 1.4% |
a | 55 | 1.3% |
system | 47 | 1.1% |
Other values (1340) | 3172 |
Most occurring characters
Value | Count | Frequency (%) |
3949 | ||
e | 2649 | 8.7% |
o | 2159 | 7.1% |
i | 2120 | 6.9% |
t | 1986 | 6.5% |
n | 1979 | 6.5% |
a | 1922 | 6.3% |
r | 1683 | 5.5% |
s | 1355 | 4.4% |
l | 1134 | 3.7% |
Other values (67) | 9661 |
Most occurring categories
Value | Count | Frequency (%) |
Lowercase Letter | 23731 | |
Space Separator | 3949 | 12.9% |
Uppercase Letter | 2475 | 8.1% |
Dash Punctuation | 163 | 0.5% |
Decimal Number | 154 | 0.5% |
Other Punctuation | 79 | 0.3% |
Open Punctuation | 21 | 0.1% |
Close Punctuation | 20 | 0.1% |
Connector Punctuation | 4 | < 0.1% |
Math Symbol | 1 | < 0.1% |
Most frequent character per category
Lowercase Letter
Value | Count | Frequency (%) |
e | 2649 | |
o | 2159 | 9.1% |
i | 2120 | 8.9% |
t | 1986 | 8.4% |
n | 1979 | 8.3% |
a | 1922 | 8.1% |
r | 1683 | 7.1% |
s | 1355 | 5.7% |
l | 1134 | 4.8% |
c | 1009 | 4.3% |
Other values (16) | 5735 |
Uppercase Letter
Value | Count | Frequency (%) |
C | 268 | |
S | 266 | |
A | 204 | 8.2% |
P | 201 | 8.1% |
R | 174 | 7.0% |
D | 164 | 6.6% |
E | 141 | 5.7% |
T | 140 | 5.7% |
F | 133 | 5.4% |
M | 127 | 5.1% |
Other values (16) | 657 |
Decimal Number
Value | Count | Frequency (%) |
1 | 33 | |
0 | 26 | |
2 | 24 | |
3 | 23 | |
6 | 13 | 8.4% |
5 | 12 | 7.8% |
9 | 8 | 5.2% |
8 | 6 | 3.9% |
4 | 5 | 3.2% |
7 | 4 | 2.6% |
Other Punctuation
Value | Count | Frequency (%) |
" | 18 | |
. | 13 | |
# | 12 | |
: | 11 | |
/ | 10 | |
, | 8 | |
% | 3 | 3.8% |
& | 3 | 3.8% |
' | 1 | 1.3% |
Space Separator
Value | Count | Frequency (%) |
3949 |
Dash Punctuation
Value | Count | Frequency (%) |
- | 163 |
Open Punctuation
Value | Count | Frequency (%) |
( | 21 |
Close Punctuation
Value | Count | Frequency (%) |
) | 20 |
Connector Punctuation
Value | Count | Frequency (%) |
_ | 4 |
Math Symbol
Value | Count | Frequency (%) |
+ | 1 |
Most occurring scripts
Value | Count | Frequency (%) |
Latin | 26206 | |
Common | 4391 | 14.4% |
Most frequent character per script
Latin
Value | Count | Frequency (%) |
e | 2649 | 10.1% |
o | 2159 | 8.2% |
i | 2120 | 8.1% |
t | 1986 | 7.6% |
n | 1979 | 7.6% |
a | 1922 | 7.3% |
r | 1683 | 6.4% |
s | 1355 | 5.2% |
l | 1134 | 4.3% |
c | 1009 | 3.9% |
Other values (42) | 8210 |
Common
Value | Count | Frequency (%) |
3949 | ||
- | 163 | 3.7% |
1 | 33 | 0.8% |
0 | 26 | 0.6% |
2 | 24 | 0.5% |
3 | 23 | 0.5% |
( | 21 | 0.5% |
) | 20 | 0.5% |
" | 18 | 0.4% |
6 | 13 | 0.3% |
Other values (15) | 101 | 2.3% |
Most occurring blocks
Value | Count | Frequency (%) |
ASCII | 30597 |
Most frequent character per block
ASCII
Value | Count | Frequency (%) |
3949 | ||
e | 2649 | 8.7% |
o | 2159 | 7.1% |
i | 2120 | 6.9% |
t | 1986 | 6.5% |
n | 1979 | 6.5% |
a | 1922 | 6.3% |
r | 1683 | 5.5% |
s | 1355 | 4.4% |
l | 1134 | 3.7% |
Other values (67) | 9661 |
출처
Categorical
HIGH CORRELATION
 
Distinct | 5 |
---|---|
Distinct (%) | 1.5% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
2018 Spring Meeting of the KNS | |
---|---|
2018 Autumn Meeting of Korean Radioactive Waste Society | |
2018 Fall Meeting of the KNS | |
2018 Spring Meeting of Korean Radioactive Waste Society | |
The Korean Association for Radiation Protection Autumn Meeting | 2 |
Length
Max length | 62 |
---|---|
Median length | 56 |
Mean length | 40.38209 |
Min length | 28 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | 2018 Autumn Meeting of Korean Radioactive Waste Society |
---|---|
2nd row | 2018 Autumn Meeting of Korean Radioactive Waste Society |
3rd row | 2018 Autumn Meeting of Korean Radioactive Waste Society |
4th row | 2018 Autumn Meeting of Korean Radioactive Waste Society |
5th row | 2018 Autumn Meeting of Korean Radioactive Waste Society |
Common Values
Value | Count | Frequency (%) |
2018 Spring Meeting of the KNS | 108 | |
2018 Autumn Meeting of Korean Radioactive Waste Society | 91 | |
2018 Fall Meeting of the KNS | 87 | |
2018 Spring Meeting of Korean Radioactive Waste Society | 47 | |
The Korean Association for Radiation Protection Autumn Meeting | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
meeting | 335 | |
2018 | 333 | |
of | 333 | |
the | 197 | |
kns | 195 | |
spring | 155 | |
korean | 140 | |
radioactive | 138 | |
waste | 138 | |
society | 138 | |
Other values (6) | 188 |
출신지
Categorical
HIGH CORRELATION
 
Distinct | 4 |
---|---|
Distinct (%) | 1.2% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Daejeon (KR) | |
---|---|
Jeju (KR) | |
Yeosu (KR) | |
Taean (KR) | 2 |
Length
Max length | 12 |
---|---|
Median length | 10 |
Mean length | 10.501493 |
Min length | 9 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | Daejeon (KR) |
---|---|
2nd row | Daejeon (KR) |
3rd row | Daejeon (KR) |
4th row | Daejeon (KR) |
5th row | Daejeon (KR) |
Common Values
Value | Count | Frequency (%) |
Daejeon (KR) | 138 | |
Jeju (KR) | 108 | |
Yeosu (KR) | 87 | |
Taean (KR) | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
kr | 335 | |
daejeon | 138 | |
jeju | 108 | 16.1% |
yeosu | 87 | 13.0% |
taean | 2 | 0.3% |
페이지
Text
Distinct | 137 |
---|---|
Distinct (%) | 40.9% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Value | Count | Frequency (%) |
p | 335 | |
2 | 75 | 11.2% |
3 | 74 | 11.0% |
4 | 41 | 6.1% |
5 | 4 | 0.6% |
74-75 | 2 | 0.3% |
116-117 | 2 | 0.3% |
27-28 | 2 | 0.3% |
161-162 | 2 | 0.3% |
29-30 | 2 | 0.3% |
Other values (127) | 131 | 19.6% |
Most occurring characters
Value | Count | Frequency (%) |
336 | ||
p | 335 | |
. | 335 | |
[ | 195 | |
] | 195 | |
3 | 183 | |
2 | 163 | |
4 | 162 | |
- | 139 | 5.5% |
5 | 95 | 3.8% |
Other values (6) | 377 |
Most occurring categories
Value | Count | Frequency (%) |
Decimal Number | 980 | |
Space Separator | 336 | 13.4% |
Lowercase Letter | 335 | 13.3% |
Other Punctuation | 335 | 13.3% |
Open Punctuation | 195 | 7.8% |
Close Punctuation | 195 | 7.8% |
Dash Punctuation | 139 | 5.5% |
Most frequent character per category
Decimal Number
Value | Count | Frequency (%) |
3 | 183 | |
2 | 163 | |
4 | 162 | |
5 | 95 | |
1 | 79 | |
7 | 75 | |
8 | 58 | 5.9% |
6 | 57 | 5.8% |
9 | 56 | 5.7% |
0 | 52 | 5.3% |
Space Separator
Value | Count | Frequency (%) |
336 |
Lowercase Letter
Value | Count | Frequency (%) |
p | 335 |
Other Punctuation
Value | Count | Frequency (%) |
. | 335 |
Open Punctuation
Value | Count | Frequency (%) |
[ | 195 |
Close Punctuation
Value | Count | Frequency (%) |
] | 195 |
Dash Punctuation
Value | Count | Frequency (%) |
- | 139 |
Most occurring scripts
Value | Count | Frequency (%) |
Common | 2180 | |
Latin | 335 | 13.3% |
Most frequent character per script
Common
Value | Count | Frequency (%) |
336 | ||
. | 335 | |
[ | 195 | |
] | 195 | |
3 | 183 | |
2 | 163 | |
4 | 162 | |
- | 139 | |
5 | 95 | 4.4% |
1 | 79 | 3.6% |
Other values (5) | 298 |
Latin
Value | Count | Frequency (%) |
p | 335 |
Most occurring blocks
Value | Count | Frequency (%) |
ASCII | 2515 |
Most frequent character per block
ASCII
Value | Count | Frequency (%) |
336 | ||
p | 335 | |
. | 335 | |
[ | 195 | |
] | 195 | |
3 | 183 | |
2 | 163 | |
4 | 162 | |
- | 139 | 5.5% |
5 | 95 | 3.8% |
Other values (6) | 377 |
언어
Categorical
CONSTANT
 
Distinct | 1 |
---|---|
Distinct (%) | 0.3% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
(EN) |
---|
Length
Max length | 4 |
---|---|
Median length | 4 |
Mean length | 4 |
Min length | 4 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | (EN) |
---|---|
2nd row | (EN) |
3rd row | (EN) |
4th row | (EN) |
5th row | (EN) |
Common Values
Value | Count | Frequency (%) |
(EN) | 335 |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
en | 335 |
소속
Categorical
HIGH CORRELATION
 
Distinct | 3 |
---|---|
Distinct (%) | 0.9% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Korean Nuclear Society, Daejeon (KR) | |
---|---|
Korean Radioactive Waste Society, Deajeon (KR) | |
Korean Association for Radiation Protection, Seoul (KR) | 2 |
Length
Max length | 55 |
---|---|
Median length | 36 |
Mean length | 40.232836 |
Min length | 36 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | Korean Radioactive Waste Society, Deajeon (KR) |
---|---|
2nd row | Korean Radioactive Waste Society, Deajeon (KR) |
3rd row | Korean Radioactive Waste Society, Deajeon (KR) |
4th row | Korean Radioactive Waste Society, Deajeon (KR) |
5th row | Korean Radioactive Waste Society, Deajeon (KR) |
Common Values
Value | Count | Frequency (%) |
Korean Nuclear Society, Daejeon (KR) | 195 | |
Korean Radioactive Waste Society, Deajeon (KR) | 138 | |
Korean Association for Radiation Protection, Seoul (KR) | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
korean | 335 | |
kr | 335 | |
society | 333 | |
nuclear | 195 | |
daejeon | 195 | |
radioactive | 138 | |
waste | 138 | |
deajeon | 138 | |
association | 2 | 0.1% |
for | 2 | 0.1% |
Other values (3) | 6 | 0.3% |
학회
Categorical
HIGH CORRELATION
 
Distinct | 5 |
---|---|
Distinct (%) | 1.5% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Proceedings of the KNS 2018 Spring Meeting | |
---|---|
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | |
Proceedings of the KNS 2018 Fall Meeting | |
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | |
Proceedings of Conference and Symposium Korean Association for Radiation Protection Autumn Meeting | 2 |
Length
Max length | 98 |
---|---|
Median length | 96 |
Mean length | 64.059701 |
Min length | 40 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 |
---|---|
2nd row | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 |
3rd row | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 |
4th row | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 |
5th row | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 |
Common Values
Value | Count | Frequency (%) |
Proceedings of the KNS 2018 Spring Meeting | 108 | |
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | 91 | |
Proceedings of the KNS 2018 Fall Meeting | 87 | |
Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | 47 | |
Proceedings of Conference and Symposium Korean Association for Radiation Protection Autumn Meeting | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
proceedings | 335 | |
meeting | 335 | |
of | 335 | |
the | 333 | |
2018 | 333 | |
kns | 195 | 6.1% |
spring | 155 | 4.9% |
symposium | 140 | 4.4% |
korean | 140 | 4.4% |
and | 140 | 4.4% |
Other values (10) | 742 |
개최지
Categorical
HIGH CORRELATION
  IMBALANCE
 
Distinct | 2 |
---|---|
Distinct (%) | 0.6% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Daejeon (KR) | |
---|---|
Seoul (KR) | 2 |
Length
Max length | 12 |
---|---|
Median length | 12 |
Mean length | 11.98806 |
Min length | 10 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | Daejeon (KR) |
---|---|
2nd row | Daejeon (KR) |
3rd row | Daejeon (KR) |
4th row | Daejeon (KR) |
5th row | Daejeon (KR) |
Common Values
Value | Count | Frequency (%) |
Daejeon (KR) | 333 | |
Seoul (KR) | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
kr | 335 | |
daejeon | 333 | |
seoul | 2 | 0.3% |
일시
Categorical
HIGH CORRELATION
 
Distinct | 4 |
---|---|
Distinct (%) | 1.2% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
18-Oct | |
---|---|
18-May | |
18-Mar | |
2009 | 2 |
Length
Max length | 6 |
---|---|
Median length | 6 |
Mean length | 5.9880597 |
Min length | 4 |
Unique
Unique | 0 ? |
---|---|
Unique (%) | 0.0% |
Sample
1st row | 18-Oct |
---|---|
2nd row | 18-Oct |
3rd row | 18-Oct |
4th row | 18-Oct |
5th row | 18-Oct |
Common Values
Value | Count | Frequency (%) |
18-Oct | 178 | |
18-May | 108 | |
18-Mar | 47 | 14.0% |
2009 | 2 | 0.6% |
Length
Common Values (Plot)
Value | Count | Frequency (%) |
18-oct | 178 | |
18-may | 108 | |
18-mar | 47 | 14.0% |
2009 | 2 | 0.6% |
키워드
Text
UNIQUE
 
Distinct | 335 |
---|---|
Distinct (%) | 100.0% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Length
Max length | 209 |
---|---|
Median length | 156 |
Mean length | 122.23284 |
Min length | 64 |
Characters and Unicode
Total characters | 40948 |
---|---|
Distinct characters | 38 |
Distinct categories | 5 ? |
Distinct scripts | 2 ? |
Distinct blocks | 1 ? |
Unique
Unique | 335 ? |
---|---|
Unique (%) | 100.0% |
Sample
1st row | SAFETY ANALYSIS; SECURITY; PROLIFERATION; NUCLEAR FACILITIES; LICENSES; CONTROL; PERFORMANCE; REACTORS |
---|---|
2nd row | CAMERAS; REPROCESSING; E-LEARNING; DETECTION; SAFEGUARDS; PERFORMANCE; IAEA; REFINING |
3rd row | REPUBLIC OF KOREA; RADIATION PROTECTION; MANAGEMENT; HUMAN POPULATIONS; NUCLEAR ENERGY; DEMAND; NUCLEAR INDUSTRY; PUBLIC OPINION; REACTORS |
4th row | SAFEGUARDS; REPROCESSING; IAEA; MONITORING; EQUIPMENT; EFFICIENCY; USES; KAERI |
5th row | SAFEGUARDS; NUCLEAR FACILITIES; USES; REACTORS; IAEA; PLANNING; REACTOR DISMANTLING |
Value | Count | Frequency (%) |
reactor | 134 | 3.0% |
nuclear | 121 | 2.7% |
reactors | 95 | 2.1% |
performance | 66 | 1.5% |
design | 64 | 1.4% |
fuel | 62 | 1.4% |
safety | 62 | 1.4% |
power | 60 | 1.4% |
uses | 54 | 1.2% |
radioactive | 53 | 1.2% |
Other values (748) | 3669 |
Most occurring characters
Value | Count | Frequency (%) |
4105 | 10.0% | |
E | 3611 | 8.8% |
I | 3062 | 7.5% |
S | 2916 | 7.1% |
A | 2872 | 7.0% |
R | 2748 | 6.7% |
T | 2724 | 6.7% |
O | 2720 | 6.6% |
; | 2643 | 6.5% |
N | 2511 | 6.1% |
Other values (28) | 11036 |
Most occurring categories
Value | Count | Frequency (%) |
Uppercase Letter | 34056 | |
Space Separator | 4105 | 10.0% |
Other Punctuation | 2643 | 6.5% |
Decimal Number | 89 | 0.2% |
Dash Punctuation | 55 | 0.1% |
Most frequent character per category
Uppercase Letter
Value | Count | Frequency (%) |
E | 3611 | |
I | 3062 | |
S | 2916 | 8.6% |
A | 2872 | 8.4% |
R | 2748 | 8.1% |
T | 2724 | 8.0% |
O | 2720 | 8.0% |
N | 2511 | 7.4% |
C | 2123 | 6.2% |
L | 1476 | 4.3% |
Other values (16) | 7293 |
Decimal Number
Value | Count | Frequency (%) |
0 | 25 | |
1 | 24 | |
6 | 13 | |
9 | 8 | 9.0% |
4 | 7 | 7.9% |
3 | 5 | 5.6% |
2 | 4 | 4.5% |
8 | 2 | 2.2% |
5 | 1 | 1.1% |
Space Separator
Value | Count | Frequency (%) |
4105 |
Other Punctuation
Value | Count | Frequency (%) |
; | 2643 |
Dash Punctuation
Value | Count | Frequency (%) |
- | 55 |
Most occurring scripts
Value | Count | Frequency (%) |
Latin | 34056 | |
Common | 6892 | 16.8% |
Most frequent character per script
Latin
Value | Count | Frequency (%) |
E | 3611 | |
I | 3062 | |
S | 2916 | 8.6% |
A | 2872 | 8.4% |
R | 2748 | 8.1% |
T | 2724 | 8.0% |
O | 2720 | 8.0% |
N | 2511 | 7.4% |
C | 2123 | 6.2% |
L | 1476 | 4.3% |
Other values (16) | 7293 |
Common
Value | Count | Frequency (%) |
4105 | ||
; | 2643 | |
- | 55 | 0.8% |
0 | 25 | 0.4% |
1 | 24 | 0.3% |
6 | 13 | 0.2% |
9 | 8 | 0.1% |
4 | 7 | 0.1% |
3 | 5 | 0.1% |
2 | 4 | 0.1% |
Other values (2) | 3 | < 0.1% |
Most occurring blocks
Value | Count | Frequency (%) |
ASCII | 40948 |
Most frequent character per block
ASCII
Value | Count | Frequency (%) |
4105 | 10.0% | |
E | 3611 | 8.8% |
I | 3062 | 7.5% |
S | 2916 | 7.1% |
A | 2872 | 7.0% |
R | 2748 | 6.7% |
T | 2724 | 6.7% |
O | 2720 | 6.6% |
; | 2643 | 6.5% |
N | 2511 | 6.1% |
Other values (28) | 11036 |
초록
Text
UNIQUE
 
Distinct | 335 |
---|---|
Distinct (%) | 100.0% |
Missing | 0 |
Missing (%) | 0.0% |
Memory size | 2.7 KiB |
Length
Max length | 1024 |
---|---|
Median length | 1024 |
Mean length | 967.22388 |
Min length | 553 |
Characters and Unicode
Total characters | 324020 |
---|---|
Distinct characters | 87 |
Distinct categories | 11 ? |
Distinct scripts | 2 ? |
Distinct blocks | 1 ? |
Unique
Unique | 335 ? |
---|---|
Unique (%) | 100.0% |
Sample
1st row | Nuclear licensees have been phasing in and implementing procedures for the regulation to comply with the standard, KINAC/RS-015. As one of the activities of the regulation, nuclear facilities licensee shall carry out the continuous assessment of the cyber security controls at least at every overhaul period to validate that the security controls developed according to the cyber security controls of KINAC Regulatory standard (RS-015) are actually applied on the site and properly working. In addition, nuclear facilities licensee shall also evaluate whether the previously established cyber security controls are effectively working in continuously changing cyber threat and environment. This paper presents how the U.S. nuclear licensees perform cyber security self-assessment and regulator's perspective to introduce and apply the method to the ROK's nuclear facilities. The cyber security self-assessment method was specifically designed for cyber security evaluations of nuclear facilities. The method can be used by l |
---|---|
2nd row | This issue about human resource is a burden not only for IAEA but also for facility operator. Therefore, it is necessary to develop algorithm that automatically detect normal and abnormal conditions in order to introduce many surveillance devices while minimizing manpower. In this study, the algorithm development was performed by using the hypothetical surveillance camera in electro-refining cell, which is the main process cell of pyroprocessing. The key technology to check operation condition automatically is to detect any object to classify normal and abnormal conditions. The movement of a crane can be an important factor in monitoring within electro-refining cell. The algorithm to detect the crane, which indicates transportation of process materials in main processes, has been developed based on the hypothetical video data showing process condition in the electro-refining cell. The study on detecting a crane in the hypothetical video obtained surveillance camera was performed. The machine learning techniqu |
3rd row | According to the emerging change on national energy transition policy in the Republic of Korea, the interest on radiation safety of domestic nuclear field has been increased. In response, it is crucial to identify the competence of human resource (HR) that could contribute to safety of radiation facility. Full scale enumeration on nuclear engineering related academic and research area had been pre-studied.The present survey analysis research is aimed to estimate expectation of human resource supply and demand on KAERI, KINS, KINAC and KHNP Central Research Institute so as to evaluate its balance status for long term stable HR management for ensuring and enhancing the radiation safety. The difference in nuclear power portion between the 4th and 8th basic plan for long-term electricity supply and demand makes difference to the HR supply. Which also leads to decreasing of HR demand from 2025 year both on KAERI and KINS. For keeping continuous balance on supply and demand of radiation safety management human reso |
4th row | A safeguards approach of the intermediate-sized pyroprocessing facility is being developed. The safeguards measures in the safeguards approach are based on the current IAEA equipment and the safeguards technology under development. The NRTA is applied to the specified area of the REPF+. The process monitoring and the C/S on the material and equipment transfer door are included to increase the effectiveness. Safeguards approach is a set of safeguards measures to allow the IAEA to meet the applicable safeguards objectives. Safeguards approaches of the existing nuclear material handling facilities were already developed, and a safeguards approach of a pyroprocessing facility is required for the effective and efficient safeguards implementation in the pyroprocessing facility. Korea Atomic Energy Research Institute (KAERI) developed the safeguards approach of a reference facility named Reference Engineering-scale Pyroprocessing Facility (REPF) in collaboration with Korea Institute of Nuclear Nonproliferation and C |
5th row | Overall safeguards activities were reviewed to be carried out during whole-life of nuclear facility. This study is applicable to most of nuclear facilities such as reactors, fuel fabrication plant, and others. Though some kind of facilities can be discussed with IAEA additionally, the above explained safeguards activities should be carried out in the legal basis. In the safeguards aspect, the status of facility function and nuclear material is the most important components. Recent issues in domestic nuclear fields are related to the decommissioning and dismantling of nuclear facilities. But safeguards activities during dismantling stage are only a part of safeguards during whole-life of facility. In this paper, safeguards implementation activities under legal basis are investigated during the wholelife of nuclear facility including the decommissioning and dismantling stage. Overall safeguards activities were reviewed to be carried out during whole-life of nuclear facility. This study is applicable to most of |
Value | Count | Frequency (%) |
the | 3651 | 7.4% |
of | 2098 | 4.3% |
and | 1534 | 3.1% |
in | 1155 | 2.3% |
to | 1154 | 2.3% |
is | 770 | 1.6% |
a | 755 | 1.5% |
for | 638 | 1.3% |
this | 464 | 0.9% |
as | 366 | 0.7% |
Other values (5999) | 36659 |
Most occurring characters
Value | Count | Frequency (%) |
48996 | ||
e | 32413 | 10.0% |
t | 23195 | 7.2% |
i | 20744 | 6.4% |
a | 20607 | 6.4% |
o | 18884 | 5.8% |
n | 18550 | 5.7% |
r | 16713 | 5.2% |
s | 16527 | 5.1% |
c | 10981 | 3.4% |
Other values (77) | 96410 |
Most occurring categories
Value | Count | Frequency (%) |
Lowercase Letter | 254166 | |
Space Separator | 48996 | 15.1% |
Uppercase Letter | 10886 | 3.4% |
Other Punctuation | 5229 | 1.6% |
Decimal Number | 2490 | 0.8% |
Dash Punctuation | 889 | 0.3% |
Close Punctuation | 589 | 0.2% |
Open Punctuation | 574 | 0.2% |
Connector Punctuation | 124 | < 0.1% |
Math Symbol | 76 | < 0.1% |
Most frequent character per category
Lowercase Letter
Value | Count | Frequency (%) |
e | 32413 | |
t | 23195 | 9.1% |
i | 20744 | 8.2% |
a | 20607 | 8.1% |
o | 18884 | 7.4% |
n | 18550 | 7.3% |
r | 16713 | 6.6% |
s | 16527 | 6.5% |
c | 10981 | 4.3% |
d | 10896 | 4.3% |
Other values (16) | 64656 |
Uppercase Letter
Value | Count | Frequency (%) |
T | 1174 | 10.8% |
S | 979 | 9.0% |
I | 896 | 8.2% |
C | 889 | 8.2% |
A | 812 | 7.5% |
R | 721 | 6.6% |
P | 546 | 5.0% |
M | 536 | 4.9% |
D | 498 | 4.6% |
F | 476 | 4.4% |
Other values (16) | 3359 |
Other Punctuation
Value | Count | Frequency (%) |
. | 2296 | |
, | 2048 | |
# | 328 | 6.3% |
" | 272 | 5.2% |
/ | 139 | 2.7% |
% | 53 | 1.0% |
: | 32 | 0.6% |
' | 25 | 0.5% |
& | 22 | 0.4% |
; | 12 | 0.2% |
Other values (2) | 2 | < 0.1% |
Decimal Number
Value | Count | Frequency (%) |
0 | 490 | |
2 | 468 | |
1 | 466 | |
3 | 266 | |
5 | 152 | 6.1% |
6 | 150 | 6.0% |
4 | 148 | 5.9% |
8 | 130 | 5.2% |
7 | 126 | 5.1% |
9 | 94 | 3.8% |
Math Symbol
Value | Count | Frequency (%) |
+ | 46 | |
= | 15 | 19.7% |
~ | 6 | 7.9% |
> | 5 | 6.6% |
< | 4 | 5.3% |
Close Punctuation
Value | Count | Frequency (%) |
) | 576 | |
] | 13 | 2.2% |
Open Punctuation
Value | Count | Frequency (%) |
( | 561 | |
[ | 13 | 2.3% |
Space Separator
Value | Count | Frequency (%) |
48996 |
Dash Punctuation
Value | Count | Frequency (%) |
- | 889 |
Connector Punctuation
Value | Count | Frequency (%) |
_ | 124 |
Modifier Symbol
Value | Count | Frequency (%) |
` | 1 |
Most occurring scripts
Value | Count | Frequency (%) |
Latin | 265052 | |
Common | 58968 | 18.2% |
Most frequent character per script
Latin
Value | Count | Frequency (%) |
e | 32413 | |
t | 23195 | 8.8% |
i | 20744 | 7.8% |
a | 20607 | 7.8% |
o | 18884 | 7.1% |
n | 18550 | 7.0% |
r | 16713 | 6.3% |
s | 16527 | 6.2% |
c | 10981 | 4.1% |
d | 10896 | 4.1% |
Other values (42) | 75542 |
Common
Value | Count | Frequency (%) |
48996 | ||
. | 2296 | 3.9% |
, | 2048 | 3.5% |
- | 889 | 1.5% |
) | 576 | 1.0% |
( | 561 | 1.0% |
0 | 490 | 0.8% |
2 | 468 | 0.8% |
1 | 466 | 0.8% |
# | 328 | 0.6% |
Other values (25) | 1850 | 3.1% |
Most occurring blocks
Value | Count | Frequency (%) |
ASCII | 324020 |
Most frequent character per block
ASCII
Value | Count | Frequency (%) |
48996 | ||
e | 32413 | 10.0% |
t | 23195 | 7.2% |
i | 20744 | 6.4% |
a | 20607 | 6.4% |
o | 18884 | 5.8% |
n | 18550 | 5.7% |
r | 16713 | 5.2% |
s | 16527 | 5.1% |
c | 10981 | 3.4% |
Other values (77) | 96410 |
출처 | 출신지 | 소속 | 학회 | 개최지 | 일시 | |
---|---|---|---|---|---|---|
출처 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 |
출신지 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 | 0.988 |
소속 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 | 0.790 |
학회 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 |
개최지 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 | 1.000 |
일시 | 1.000 | 0.988 | 0.790 | 1.000 | 1.000 | 1.000 |
개최지 | 학회 | 일시 | 출처 | 소속 | 출신지 | |
---|---|---|---|---|---|---|
개최지 | 1.000 | 0.995 | 0.997 | 0.995 | 0.998 | 0.997 |
학회 | 0.995 | 1.000 | 0.998 | 1.000 | 0.997 | 0.998 |
일시 | 0.997 | 0.998 | 1.000 | 0.998 | 0.849 | 0.848 |
출처 | 0.995 | 1.000 | 0.998 | 1.000 | 0.997 | 0.998 |
소속 | 0.998 | 0.997 | 0.849 | 0.997 | 1.000 | 0.998 |
출신지 | 0.997 | 0.998 | 0.848 | 0.998 | 0.998 | 1.000 |
출처 | 출신지 | 소속 | 학회 | 개최지 | 일시 | |
---|---|---|---|---|---|---|
출처 | 1.000 | 0.998 | 0.997 | 1.000 | 0.995 | 0.998 |
출신지 | 0.998 | 1.000 | 0.998 | 0.998 | 0.997 | 0.848 |
소속 | 0.997 | 0.998 | 1.000 | 0.997 | 0.998 | 0.849 |
학회 | 1.000 | 0.998 | 0.997 | 1.000 | 0.995 | 0.998 |
개최지 | 0.995 | 0.997 | 0.998 | 0.995 | 1.000 | 0.997 |
일시 | 0.998 | 0.848 | 0.849 | 0.998 | 0.997 | 1.000 |
저자 | 제목 | 출처 | 출신지 | 페이지 | 언어 | 소속 | 학회 | 개최지 | 일시 | 키워드 | 초록 | |
---|---|---|---|---|---|---|---|---|---|---|---|---|
0 | Lee, Chae Chang (Korea Institute of Nuclear Nonproliferation and Control, Daejeon (KR)) | Review of the US cyber security self-assessment method from the regulatory perspective | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 27-28 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | SAFETY ANALYSIS; SECURITY; PROLIFERATION; NUCLEAR FACILITIES; LICENSES; CONTROL; PERFORMANCE; REACTORS | Nuclear licensees have been phasing in and implementing procedures for the regulation to comply with the standard, KINAC/RS-015. As one of the activities of the regulation, nuclear facilities licensee shall carry out the continuous assessment of the cyber security controls at least at every overhaul period to validate that the security controls developed according to the cyber security controls of KINAC Regulatory standard (RS-015) are actually applied on the site and properly working. In addition, nuclear facilities licensee shall also evaluate whether the previously established cyber security controls are effectively working in continuously changing cyber threat and environment. This paper presents how the U.S. nuclear licensees perform cyber security self-assessment and regulator's perspective to introduce and apply the method to the ROK's nuclear facilities. The cyber security self-assessment method was specifically designed for cyber security evaluations of nuclear facilities. The method can be used by l |
1 | Won, Byung Hee; Park, Se Hwan; Shin, Hee Sung; Ahn, Seong Kyu (Korea Atomic Energy Research Institute, Daejeon (KR)) | Algorithm development for detecting a crane on surveillance camera in pyroprocessing based on machine learning technique | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 29-30 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | CAMERAS; REPROCESSING; E-LEARNING; DETECTION; SAFEGUARDS; PERFORMANCE; IAEA; REFINING | This issue about human resource is a burden not only for IAEA but also for facility operator. Therefore, it is necessary to develop algorithm that automatically detect normal and abnormal conditions in order to introduce many surveillance devices while minimizing manpower. In this study, the algorithm development was performed by using the hypothetical surveillance camera in electro-refining cell, which is the main process cell of pyroprocessing. The key technology to check operation condition automatically is to detect any object to classify normal and abnormal conditions. The movement of a crane can be an important factor in monitoring within electro-refining cell. The algorithm to detect the crane, which indicates transportation of process materials in main processes, has been developed based on the hypothetical video data showing process condition in the electro-refining cell. The study on detecting a crane in the hypothetical video obtained surveillance camera was performed. The machine learning techniqu |
2 | Lee, Dong Hyun; Lee, Man Ki; Kim, Hee Reyoung; Min, Byung Joo (Ulsan National Institute of Science and Technology, Ulsan (KR)) | Current status of management of human resource for enhancement of radiation safety | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 33-34 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | REPUBLIC OF KOREA; RADIATION PROTECTION; MANAGEMENT; HUMAN POPULATIONS; NUCLEAR ENERGY; DEMAND; NUCLEAR INDUSTRY; PUBLIC OPINION; REACTORS | According to the emerging change on national energy transition policy in the Republic of Korea, the interest on radiation safety of domestic nuclear field has been increased. In response, it is crucial to identify the competence of human resource (HR) that could contribute to safety of radiation facility. Full scale enumeration on nuclear engineering related academic and research area had been pre-studied.The present survey analysis research is aimed to estimate expectation of human resource supply and demand on KAERI, KINS, KINAC and KHNP Central Research Institute so as to evaluate its balance status for long term stable HR management for ensuring and enhancing the radiation safety. The difference in nuclear power portion between the 4th and 8th basic plan for long-term electricity supply and demand makes difference to the HR supply. Which also leads to decreasing of HR demand from 2025 year both on KAERI and KINS. For keeping continuous balance on supply and demand of radiation safety management human reso |
3 | Park, Se Hwan; Kim, Ho Dong; Lee, Chae Hoon; Song, Dae Yong; Won, Byung Hee; Ahn, Seong Kyu (Korea Atomic Energy Research Institute, Daejeon (KR)); (Chonbuk National University, Jeonju (KR)) | Development of safeguards approach of intermediate-sized pyroprocessing facility | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 37-38 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | SAFEGUARDS; REPROCESSING; IAEA; MONITORING; EQUIPMENT; EFFICIENCY; USES; KAERI | A safeguards approach of the intermediate-sized pyroprocessing facility is being developed. The safeguards measures in the safeguards approach are based on the current IAEA equipment and the safeguards technology under development. The NRTA is applied to the specified area of the REPF+. The process monitoring and the C/S on the material and equipment transfer door are included to increase the effectiveness. Safeguards approach is a set of safeguards measures to allow the IAEA to meet the applicable safeguards objectives. Safeguards approaches of the existing nuclear material handling facilities were already developed, and a safeguards approach of a pyroprocessing facility is required for the effective and efficient safeguards implementation in the pyroprocessing facility. Korea Atomic Energy Research Institute (KAERI) developed the safeguards approach of a reference facility named Reference Engineering-scale Pyroprocessing Facility (REPF) in collaboration with Korea Institute of Nuclear Nonproliferation and C |
4 | Lee, Sung Ho; Kim, In Chul; Lee, Byung Doo; Kim, Hyun Jo; Kim, Hyun Sook; Jung, Juang (Korea Atomic Energy Research Institute, Daejeon (KR)) | A study on the safeguards of nuclear facility during whole-life | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 39-40 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | SAFEGUARDS; NUCLEAR FACILITIES; USES; REACTORS; IAEA; PLANNING; REACTOR DISMANTLING | Overall safeguards activities were reviewed to be carried out during whole-life of nuclear facility. This study is applicable to most of nuclear facilities such as reactors, fuel fabrication plant, and others. Though some kind of facilities can be discussed with IAEA additionally, the above explained safeguards activities should be carried out in the legal basis. In the safeguards aspect, the status of facility function and nuclear material is the most important components. Recent issues in domestic nuclear fields are related to the decommissioning and dismantling of nuclear facilities. But safeguards activities during dismantling stage are only a part of safeguards during whole-life of facility. In this paper, safeguards implementation activities under legal basis are investigated during the wholelife of nuclear facility including the decommissioning and dismantling stage. Overall safeguards activities were reviewed to be carried out during whole-life of nuclear facility. This study is applicable to most of |
5 | Lee, Dae Sung; Bang, Jae Young (Korea Atomic Energy Research Institute, Daejeon (KR)) | Legal case study about the lawsuit to the Korea government's 8th basic plan for electricity supply and demand | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 47-48 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | PLANNING; REPUBLIC OF KOREA; LAWS; SUPPLY AND DEMAND; ELECTRICITY; RADIATION PROTECTION; NUCLEAR DISARMAMENT; NUCLEAR INDUSTRY; REACTOR ACCIDENTS | Since the 2011 Fukushima nuclear accident and the 2016 Kyongju earthquake, domestic concern for nuclear power has grown rapidly and demands for nuclear safety have come to the fore. As a result, the current government has announced the eighth basic plan for power supply in 2017, which has a lot of radical changes. This has led to disagreements among related stakeholders, leading to legal disputes. In this study, we will review the basic outline of the Eighth Basic Plan for Electricity Supply and Demand, and analyze main legal issues of administrative revocation lawsuit against the Korea government for cancelling the Plan. In the future, the court will closely examine whether the plan has the disposition power to be the object of the administrative litigation and whether the plaintiffs are qualified as specific and direct victims of the plan. This lawsuit shall be a very meaningful legal case in the fields of legal academy and nuclear industry |
6 | Lee, Jin Young (Korea Institute of Nuclear Non-Proliferation and Control, Daejeon (KR)) | The education and training activities and future challenges of INSA in ROK | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 49-50 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | TRAINING; REPUBLIC OF KOREA; SAFEGUARDS; SAFETY; PROLIFERATION; COOPERATION; EFFICIENCY; ENERGY POLICY | Domestic safeguards implementation activities of ROK are implemented based on the Nuclear Safety Act. It emphasize the importance of education and training with respect to nuclear non-proliferation. ROK has used education and training activities as an important means to strengthen international nuclear non-proliferation regime and cooperate with the international community and implement domestic safeguards activities effectively. With the establishment of International Nuclear Nonproliferation and Security Academy (INSA), ROK started an international and domestic education and training regarding nuclear non-proliferation in earnest. Finally, INSA will keep accomplishing its original mission to strengthen international nuclear nonproliferation regime by providing international and domestic education and training with active utilization of new technology. INSA will keep its sustainability by means of two measures; development tailored education and training program for newcomer countries; enhancing INSA's outre |
7 | Kim, Ki Hwan; Ha, Seong Jun; Mun, Seung Uk; Kim, Jong Hwan; Ko, Young Mo; Park, Jeong Yong (Korea Atomic Energy Research Institute, Daejeon (KR)) | Characterization of U-Zr system fuel melt residue for recycle of metallic fuel scarp | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 71-72 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | SODIUM COOLED REACTORS; FUEL RODS; FABRICATION; CASTING; RECYCLING; INJECTION; SURFACES; FEASIBILITY STUDIES | The injection casting method has the advantages of high productivity and excellent remote control, but the drawback of low yield of about 50%. In this study, the characteristics of the residue scraps of U-Zr alloy system fuel in as-cast state and after surface treatment such as mechanical and chemical treatment have been examined to evaluate the feasibility the recycle of the fuel scraps, in order to improve the yield during the fuel fabrication process. In further, metallic fuel slugs were refabricated using recycled metallic fuel scraps by injection casting method. The characteristics of the melt residue scraps of UZr alloy system fuel in as-cast state and after surface treatment have been examined to evaluate the feasibility the recycle of the fuel scraps. Surface impurity layers on the surface have been removed on the whole after mechanical treatment. Surface impurity layers on the surface have been removed on the whole after mechanical treatment. Metallic fuel slugs were also re-fabricated soundly with m |
8 | Lim, Suk Nam; Shin, Gyung Wook; Chae, Gyung Sun; Park, Jae Seok (SAE-AN ENGINEERING Co., Seoul (KR)) | Evaluation of acceptance criterion for dryness of canister and spent nuclear fuel for dry storage | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 75-76 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | SPENT FUELS; DRY STORAGE; CONTAINERS; VAPORS; BURNUP; MOISTURE; WATER; REGULATIONS; FUEL ASSEMBLIES | Canister is considered to be dry when the temperature of the gas exiting the freezer or canister exit gas is below the preset temperature or DP for 30 minutes which correspond to the partial pressure of the water vapor in the canister of less than 3 torr. As the transition to storing the spent nuclear fuel (SNF) from spent fuel pool in dry storage facilities for extended period, NPPs must be prepared to dry SNFs. The Forced Helium Dehydration (FHD) technology has been developing to preserve the integrity of SNFs and fuel storage system as a R&D project of KETEP. FHD drying is specified for a canister that contains high-burn up fuel assembly. For commercial SNF, the typical acceptance criterion nis maintaining a 3.0 torr pressure for 30 minutes. Adequacy of water removal should be evaluated by pressure rebounding measurement or monitoring the moisture content in process gas removed from the dried container. Monitoring the moisture content in process gasmethod can be used for FHD drying. It is necessary to sele |
9 | Kim, Ho A; Kim, Yong Soo (Hanyang University, Seoul (KR)); Noh, Jae Soo (Atomic Creative Technology Co., Ltd., Daejeon (KR)); Kim, Ju Seong (Korea Atomic Energy Research Institute, Daejeon (KR)) | Effect of hydride re-orientation and hydride rim on fracture energy of Zircaloy-4 cladding | 2018 Autumn Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 77-78 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Autumn Meeting 2018 | Daejeon (KR) | 18-Oct | HYDRIDES; ZIRCALOY 4; CLADDING; SPENT FUELS; COOLING; DRY STORAGE; MORPHOLOGY | Some phenomena, such as hydride rim and hydride re-orientation, can occur in SNF claddings and they can worse the integrity of the claddings more than uniformly precipitated hydrides. In this study, hydrogen charging and hydride re-orientation treatment were implemented to simulate SNF claddings and ring compression tests were adopted as a test method to evaluate the fracture energy of claddings which shall be subjected to shock loads during transportation. Then, effects of hydride re-orientation and hydride rim on fracture energy were analyzed based on the RCT results. RCTs were conducted using uniform hydride specimens and hydride rim specimens treated hydride re-orientation in 90-150 MPa at a temperature ranges from RT to 200 degrees C. Mechanical properties of SNF claddings were evaluated on two parameters, The fracture energy/area at RT, 100 degrees C and 150 degrees C decreases with an increase in the RHCF. The fracture energy/area at RT, 100#DBC2##DF07# and 150#DBC2##DF07# decreases with an increase in |
저자 | 제목 | 출처 | 출신지 | 페이지 | 언어 | 소속 | 학회 | 개최지 | 일시 | 키워드 | 초록 | |
---|---|---|---|---|---|---|---|---|---|---|---|---|
325 | Rashid, Nur Shahidah Abdul; Um, Woo Yong (Div. of Advanced Nuclear Engineering (DANE), Pohang University of Science and Technology (POSTECH), Pohang (KR)); Siong, Khoo Kok; Saleh, Zetty Izzaty; Mahzan, Nurul Syiffa; Fadzil, Syazwani Mohd (School of Applied Physics, Faculty of Science and Technology, Universiti Kebangsaan Malaysia (UKM), Selangor (ML)) | Radiological risk assessment of "2"3"2Th and "2"3"8U in water leach purification((WLP) residue using modified SPLP method | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 355-356 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | RISK ASSESSMENT; THORIUM 232; URANIUM 238; PURIFICATION; MODIFICATIONS; RADIATION DOSES; UPTAKE | The water leach purification (WLP) residue contain radioactive elements such as thorium ("2"3"2Th) and uranium ("2"3"8U). The aim of this case study is to estimate potential level of "2"3"2Th and "2"3"8U in WLP residue to enter the human body using modified Synthetic Precipitation Procedure (SPLP) (Method 1312). In order to determine potential radiation doses hence taking measures to evade radiation exposure to consumers, it is vital to evaluate the radionuclides content of WLP residue. Additionally, knowledge of "2"3"2Th and "2"3"8U daily intake are crucial for evaluating metabolic parameters of radionuclides uptake and retention in human body. "2"3"2Th and "2"3"8U concentrations have been evaluated by using modified SPLP method. The maximum concentrations of "2"3"2Th (8.23 mg kg"-"1) and "2"3"8U (0.363 mg kg"-"1) in WLP residue were found at low pH (= 4), while the leached amounts of "2"3"8U and "2"3"2Th were minimum at pH 7 and 8 conditions. |
326 | Lee, Hae Cho; Lee, G. Y.; Kim, J. S.; Kim, H. K.; Kim, B. S.; Kim, J. S.; Lee, G. H.; Baek, S. Y. (Korea Atomic Energy Research Institute, Daejeon (KR)); Heo, W. S.; Sohn, K. Y. (MIRAEEN Co., Ltd.,Daejeon (KR)) | Establishment of alarm management system for radiation emergency response | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 369-370 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | ALARM SYSTEMS; MANAGEMENT; ACCIDENTS; RADIATIONS; PERFORMANCE; ENVIRONMENT; SAFETY; EFFICIENCY | In the event of a radiation emergency, information sharing and rapid propagation of the radiation emergency should be done promptly in order to effectively perform emergency response in the early stage from this point of view, this study describes an AMP (Alarm Manager Program) to disseminate the emergency situation early and call the designated emergency responders when the radiation level of the facility or environment rises to the emergency level. Radiation emergency response should be established to ensure that the protection of lives is swiftly handled. The construction of a system to realize such a purpose must be established to enable rapid emergency response. For this purpose, the AMS of this study is expected to be used effectively in the emergency personnel call-up by spreading the situation quickly in case of radiation emergency |
327 | Kim, Jong Soo; Lee, Sung Ho; Kwon, O Young; Lee, Hae Cho (Korea Atomic Energy Research Institute, Daejeon (KR)) | Development of air suction control system for continuous air contamination monitor | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 371-372 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | CONTROL SYSTEMS; AIR; CONTAMINATION; MONITORS; NUCLEAR FACILITIES; RADIOACTIVE MATERIALS; INTAKE; ERRORS | In this paper, an air suction control system for covering a relatively wide area is considered. Most of air contamination monitoring is used air suction pathway of single channel. In the other side, the ASCS can be applied several air suction channels for the radioactive substance treatment laboratory of a large area. It will more effect than single channel method. Equipment to be used a nuclear facility should be analyzed for error to recover quickly. In this point of view, the ASCS analyzed the possible errors and proved them through experiments |
328 | Lee, Ki Man; Park, Byung Gun; Sun, Gwang Min (Korea Atomic Energy Research Institute, Daejeon (KR)) | A preliminary study for residual radioactivity assessment after neutron irradiation of silicon carbide | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 377-378 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | RADIOACTIVITY; NEUTRONS; IRRADIATION; SILICON CARBIDES; SUBSTRATES; THERMODYNAMIC PROPERTIES; ELECTRICAL PROPERTIES; TRANSMUTATION; SAFETY; QUALITY CONTROL; MONTE CARLO METHOD; IMPURITIES | Silicon carbide (SiC) single crystal has been an excellent substrate material for high power and high frequency electronic devices because of its excellent thermal and electrical properties compared with silicon. Neutron transmutation doping (NTD) of semiconductors is an important method for applications that require high dopant homogeneity, for example in electric power devices. For neutron transmutation doping, SiC is irradiated by neutron and the components of SiC become radioactive nuclides. These radioactive nuclides can be a problem for safety and quality control. In this study, assessment of residual radioactivity after neutron irradiation of SiC is conducted using Monte Carlo simulation and most influential component is discussed. Assessment for residual radioactivity after neutron irradiation of SiC is conducted using PHITS simulation. As a result, aluminum that is an impurity in SiC has dominant residual radioactivity and ambient dose equivalent after neutron irradiation. Thus the concentration of a |
329 | Jin, Hyung Gon; Lee, Dong Won; Yoon, Jae Sung; Kim, Suk Kwon; Lee, Eo Hwak; Park, Seong Dae; Shin, Chang Wook (Korea Atomic Energy Research Institute, Daejeon (KR)); Cho, Seung Yon (National Fusion Research Institute, Daejeon (KR)) | Tritium release under unlikely and extremely unlikely loading condition of the HCCR TBS at PD-1 Phase | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 395-396 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | TRITIUM; ITER TOKAMAK; COOLING SYSTEMS; SAFETY; DESIGN; PIPES; DATA | Tritium is one of the most highly permeable molecule on earth, therefore, tritium permeation takes place from HCCR TBS. This paper presents a tritium release input data set of unlikely and extremely unlikely loading condition for the HCCR TBS, assumption of the estimation and boundary conditions. This result is outcome of input data set for the ITER Connection Pipe System Design Document, which contains total activity(Bq) of each location and amount of tritium(mg) for unlikely and extremely unlikely loading conditions of the HCCR TBS. At the PD-1 stage, it is conservatively assumed that tritium in pipes completely releases during unlikely and extremely unlikely loading. Amount of tritium highly depends on operating temperature of pipes in each room. Total activity and tritium amount have been estimated. |
330 | Yoon, Kyoung Won; Yoo, Jin; Jang, Mi Suk; Kim, Seong Rae (Nuclear Engineering Service and Solution Co., Ltd., Daejeon (KR)) | Vacuum suction force analysis of concrete wall climbing device for dry cask storage system | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 397-398 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | CONCRETES; INSPECTION; DRY STORAGE; CASKS; SENSORS; DESIGN; ADSORPTION; SHAPE; SURFACES; RADIATIONS | Sensor transport system(SeTS) is the wall climbing instrument developing to inspect the defects of dry cask storage system(DCSS) wall. An impeller and a lower chamber of impeller were selected as the calculation area in this analysis. The analysis conditions were selected in consideration of the suction motor specification and the lower chamber of impeller was simulated in the flow range with the highest efficiency of the impeller. In this paper, we have examined the capacity of SeTS equipped with some sensors and accessories and climbing the walls using CFD code. As a result, the impeller with 10 blades, 7,600 rpm speed and 0.0198kg/s flow rate was evaluated to be able to mount up to 3.8kg excluding device when the gap between the wall surface and chamber is 5mm. If sensors and accessories are determined in the future, the final design will be carried out through additional analysis that reflects these conditions. |
331 | Ji, Young Yong; Chung, Kun Ho; Kang, Mun Ja; Lee, Wan No (Korea Atomic Energy Research Institute, Daejeon (KR)); Lim, Tae Hyung (SI Detection Co. Ltd., Daejeon (KR)) | The determination of depth distributions of radioactive cesium in the ground using in situ gamma-ray spectrometry | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 401-402 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | CESIUM; DEPTH; SPATIAL DISTRIBUTION; GAMMA RADIATION; SPECTROSCOPY; SAMPLING; ALGORITHMS; COLLIMATORS; HIGH-PURITY GE DETECTORS; COMPUTER CALCULATIONS; ENERGY SPECTRA | In situ measurements with specific algorithms and hardware, which means multiple photopeaks, peak-to-valley, and collimation method, have been using to estimate the depth distribution of nuclides in the ground. In this study, a simple method to estimate the depth distributions of nuclides was developed by calculating the individual dose rate of detected gamma nuclides at 1 m above the ground. The dose rate spectroscopy was then used to previously determine the individual dose rate of "1"3"7Cs from the measured energy spectrum using a portable HPGe detector. In addition, theoretical individual dose rates of "1"3"7Cs at 1 m above the ground were calculated by assuming several depth distributions of "1"3"7Cs in the ground. The real depth distribution of "1"3"7Cs was determined from the comparison between them. Its radioactivity in the ground was then calculated by applying the dose conversion factor in the unit of nGy/h/Bq/m"2 in the condition of the determined depth distribution. |
332 | Jeong, Keun Hong (Dept. of Chemistry, Korea Military Academy, Seoul (KR)); Cha, Wan Sik (Nuclear Chemistry Research Division, Korea Atomic Energy Research Institute, Daejeon (KR)); Kwak, Kyoung Won (Center for Molecular Spectroscopy and Dynamics, Institute for Basic Science (IBS), Seoul (KR)) | DFT study on the U(IV)-PNPP complex in water | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 407-408 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | WATER; TOXICITY; RADIOACTIVE WASTES; PHOSPHATES; BIOCHEMISTRY; CHEMICAL PROPERTIES; PERFORMANCE; USES; ACTINIDES | Both experimental and theoretical studies have discussed complexation with various ligands. However, paraNitrophenylphosphate (PNPP) was not dealt with U(IV) in complexation study even though PNPP is one of the important substrates for phosphate binding chemistry at mineral-water interfaces and spectrophotometric biochemical assays. Computational chemistry is a great complement to experimental studies of U(IV) chemistry because this methodology provides valuable information that is not available through the experiment, especially for transient materials and those with short kinetic times. Herein, we performed theoretical studies to obtain several important chemical properties of U(IV)- PNPP complex in water including their stable structures, spin state, and infrared spectra. This computational study may be a firm basis for the future applications on environmental researches of U(IV) and actinide chemistry in water |
333 | Cha, Wan Sik; Kim, Hee Kyung; Hong, Sue Young; Jung, Euo Chang (Korea Atomic Energy Research Institute, Daejeon (KR)) | Luminescence studies of U(VI)-laponite system in aqueous phase | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 417-418 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | LUMINESCENCE; SURFACES; ADSORPTION; RADIOISOTOPES; SAFETY ANALYSIS; WASTE DISPOSAL; SORPTION; MINERALS; FLUORESCENCE SPECTROSCOPY; ELECTROLYTES | In this study, we attempt to understand the basic U(VI) luminescence characteristics arising from the interaction with a synthetic nano-clay mineral, i.e., Laponite RD#Registered Sign#. Although laponite shares a 2:1 silicate structure with the smectite natural clays such as montmorillonite, its primary particles are fairly monodispersed with a disk-like shape having diameter in the range 25-30 nm and thickness of 0.92 nm. So, it offers a large area of surface binding sites, particularly from the edge of the platelet structures. At low concentration it can form a homogeneous and transparent aqueous solution depending on pH and electrolyte concentrations (ionic strength). Thus, U(VI)-laponite system can be a good model system for investigating U(VI)-clay interactions and speciation using TRLFS. By using a synthetic nano-clay mineral material (laponite) and TRLFS techniques the fundamental sorption behaviors of U(VI) were investigated. |
334 | Kim, Jung Suk; Park, Yang Soon; Kang, Byung Man; Suh, Kyung Won; Choi, Kwang Soon; Ha, Yeong Keong (Korea Atomic Energy Research Institute, Daejeon (KR)) | Determination of cerium isotopes and total burnup in irradiated pellet based on isotope dilution mass spectrometric measurement | 2018 Spring Meeting of Korean Radioactive Waste Society | Daejeon (KR) | p. 425-426 | (EN) | Korean Radioactive Waste Society, Deajeon (KR) | Proceedings of the Conference and Symposium Korean Radioactive Waste Society Spring Meeting 2018 | Daejeon (KR) | 18-Mar | BURNUP; PELLETS; ISOTOPE DILUTION; MASS SPECTROSCOPY; IRRADIATION; VALIDATION; MONITORS; ISOTOPE RATIO | Burnup determination by destructive method, which is based on the determination of specific nuclides, e.g. U, Pu and "1"4"8Nd by a chemical analysis after an appropriate separation of the heavy elements and a monitoring of the fission product, is widely used as a reference method to measure the burnup of an irradiated fuel. The aim of the present work is to determine the isotopic compositions and its contents of Ce for the samples from sintered solid and annular pellets of PWR type irradiated in the Hanaro reactor at KAERI, and to determine the total burnup using the measured results, so as to determine the respective validity of the methods. The contents of U, Pu, Nd, Ce and their isotopes in irradiated pellet samples and the total burnup by using Nd and Ce isotope monitors can be determined simultaneously by the isotope dilution mass spectrometric techniques. The Nd and Ce isotope patterns provide information on the real irradiation characteristics which are necessary for evaluating a fuel's performance in |