TY - GEN
T1 - PWR SPENT FUEL DRY STORAGE LOADING PATTERN and SAFETY EVALUATION
AU - Jinghui, Gao
AU - Wen, Li
AU - Gang, Li
AU - Shengdong, Zhong
AU - Jin, Xu
AU - Bingquan, Zhao
N1 - Publisher Copyright:
© 2022 by ASME.
PY - 2022
Y1 - 2022
N2 - This paper describes the loading pattern, safety evaluation and operating experiences of PWR plant off-site Spent Fuel Dry Storage System (SFDSS). According to the limits from the SFDSS criticality and heat-Transfer safety analysis, ALARA principle and AFA series fuel characteristics, technical staff complete the loading pattern and safety evaluation by analyzing influence of assemblies initial enrichment, burn up and cooling time. This paper also shows the temperature and dose data during AFA series fuel SFDSS loading, transportation and storage, which can indicate the actual condition of SFDSS criticality, heattransfer and radiation. In general, AFA series fuel SFDSS is in good condition and meet the expected design and safety requirements.
AB - This paper describes the loading pattern, safety evaluation and operating experiences of PWR plant off-site Spent Fuel Dry Storage System (SFDSS). According to the limits from the SFDSS criticality and heat-Transfer safety analysis, ALARA principle and AFA series fuel characteristics, technical staff complete the loading pattern and safety evaluation by analyzing influence of assemblies initial enrichment, burn up and cooling time. This paper also shows the temperature and dose data during AFA series fuel SFDSS loading, transportation and storage, which can indicate the actual condition of SFDSS criticality, heattransfer and radiation. In general, AFA series fuel SFDSS is in good condition and meet the expected design and safety requirements.
KW - Dry storage
KW - Loading pattern
KW - Operating experience
KW - PWR
KW - Safety evaluation
KW - Spent fuel
UR - https://www.scopus.com/pages/publications/85143176778
U2 - 10.1115/ICONE29-93351
DO - 10.1115/ICONE29-93351
M3 - 会议稿件
AN - SCOPUS:85143176778
SN - 9784888982566
T3 - International Conference on Nuclear Engineering, Proceedings, ICONE
BT - Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology
PB - American Society of Mechanical Engineers (ASME)
T2 - 2022 29th International Conference on Nuclear Engineering, ICONE 2022
Y2 - 8 August 2022 through 12 August 2022
ER -