Realistic evaluation of source terms for steam generator tube rupture accidents

被引:2
|
作者
Shin, Hoyoung [1 ]
Jae, Moosung [1 ]
机构
[1] Hanyang Univ, Dept Nucl Engn, 418 HIT,222 Wangsimni Ro, Seoul 04763, South Korea
关键词
Decomposition Event Tree (DET); Source Term Category (STC); Level 2 Probabilistic Safety Assessment (PSA); Steam Generator Tube Rupture (SGTR) without fission product release;
D O I
10.1016/j.anucene.2021.108559
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
In the existing Probabilistic Safety Assessment (PSA) model, all the Steam Generator Tube Rupture (SGTR) sequences have been assumed to have identical fission product release characteristics without considering the sequences of no source term release resulting in a conservative evaluation. Since the Korean Nuclear Safety Act was revised in 2016, a realistic method that can reasonably evaluate the risk became needed to satisfy the PSA targets. Therefore, a new method is proposed to improve the Level 2 PSA model (decomposition event tree, containment event tree, source term category logic diagram) that can identify the SGTR sequences without fission product release to the environment. The sequences are classified by dividing the Source Term Category (STC) of SGTRs into SGTR_CON (containment) and SGTR_ENV (environment). If fission product is trapped inside the containment building and not released to the environment, it is classified as SGTR_CON. Otherwise it is classified as SGTR_ENV. About 72% of the existing STC for SGTR is treated as SGTR_CON, which does not release fission product to the environment. If SGTR STCs are divided into SGTR-CON and SGTR-ENV, then a more reasonable source term evaluation of SGTR sequences is expected. (c) 2021 Published by Elsevier Ltd.
引用
收藏
页数:12
相关论文
共 50 条
  • [41] Safety evaluation of Multiple Steam Generator Tube rupture accident using the best estimate plus uncertainty approach
    Dzien, Sebastian
    Diab, Aya
    NUCLEAR ENGINEERING AND DESIGN, 2024, 422
  • [42] Factors influencing the potential for steam generator tube rupture in pressurized water reactors
    Knudson, DL
    Ghan, LS
    PROBABILISTIC SAFETY ASSESSMENT AND MANAGEMENT (PSAM 4), VOLS 1-4, 1998, : 2879 - 2884
  • [43] The Analysis of Severe Accident Induced Steam Generator Tube Rupture and LERF Risk
    Peng, Chang-Hong
    Yang, Ying-Hao
    ADVANCES IN POWER AND ELECTRICAL ENGINEERING, PTS 1 AND 2, 2013, 614-615 : 626 - +
  • [44] Steam generator tube rupture simulation using extended finite element method
    Mohanty, Subhasish
    Majumdar, Saurin
    Natesan, Ken
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 697 - 705
  • [45] RADIOACTIVITY RELEASE VERSUS PROBABILITY FOR A STEAM-GENERATOR TUBE RUPTURE ACCIDENT
    BUSLIK, AJ
    HALL, RE
    NUCLEAR TECHNOLOGY, 1979, 46 (03) : 566 - 570
  • [46] RETRAN-02 ANALYSIS OF STEAM-GENERATOR TUBE RUPTURE FOR KEWAUNEE
    KIM, MH
    HAMMER, KE
    BARRY, J
    COEN, E
    CORRADINI, ML
    MOSES, GA
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1984, 47 : 507 - 509
  • [47] Effects of tube rupture modeling and the parameters on the analysis of multiple steam generator tube rupture event progression in APR1400
    Jeong, JH
    Choi, KY
    NUCLEAR ENGINEERING AND DESIGN, 2003, 224 (03) : 313 - 336
  • [48] Evaluation of Limit Loads for Surface Cracks in the Steam Generator Tube
    Kim, Hyun-Su
    Kim, Jong-Sung
    Jin, Tae-Eun
    Kim, Hong-Deok
    Chung, Han-Sup
    TRANSACTIONS OF THE KOREAN SOCIETY OF MECHANICAL ENGINEERS A, 2006, 30 (08) : 993 - 1000
  • [49] Evaluation of cancer risk after a release from a hypothetical nuclear reactor steam generator tube rupture accident (SGTR)
    Andrade, Edson R.
    Stenders, Ricardo
    Castro, Mariana S. C.
    Santos, Catharina V. V.
    Prah, Matjaz
    Silva, Ademir X.
    ANNALS OF NUCLEAR ENERGY, 2020, 136
  • [50] MELCOR analysis of steam generator tube creep rupture in station blackout severe accident
    Liao, Y
    Vierow, K
    NUCLEAR TECHNOLOGY, 2005, 152 (03) : 302 - 313