Severe accident analysis to verify the effectiveness of severe accident management guidelines for large pressurized heavy water reactor

被引:2
|
作者
Gokhale, O. S. [1 ]
Mukhopadhyay, D. [1 ]
Lele, H. G. [1 ]
Singh, R. K. [1 ]
机构
[1] Bhabha Atom Res Ctr, Reactor Safety Div, Bombay 400085, Maharashtra, India
关键词
Abbreviations; ASDV; atmospheric steam discharge valves; calandria tube; calandria vessel; CT; CV; ECCS; emergency core cooling system; emergency operating procedure; EOP; IH; inlet header; main steam-line safety valve; MSSV; OH; OPRD; outlet header; over pressure rupture disk; PCP; PHTS; PHWR; pressure tube; pressurized heavy water reactor; primary circulation pump; primary heat transport system; PT; RD; rupture disk; SAMG; SBO; severe accident management guidelines; SG; station black out; steam generator;
D O I
10.1016/j.nucengdes.2014.06.039
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
The pressurized heavy water reactor (PHWR) contains both inherent and engineered safety features that help the reactor become resistant to severe accident and its consequences. However in case of a low frequency severe accident, despite the safety features, procedural action should be in place to mitigate the accident progression. Severe accident analysis of such low frequency event provides insight into the accident progression and basis to develop the severe accident management guidelines (SAMG). Since the order of uncertainty in the progression path of severe accident is very high, it is necessary to study the consequences of the SAMG actions prescribed. The paper discusses severe accident analysis for large PHWRs for multiple failure transients involving a high pressure scenario (initiation event like SBO with loss of emergency core cooling system and loss of moderator cooling). SAMG actions prescribed for such a scenario include water injection into steam generator, calandria vessel or calandria vault at different stages of accident. The effectiveness of SAMG actions prescribed has been investigated. It is found that there is sufficient time margin available to the operator to execute these SAMG actions and the progression of severe accident is arrested in all the three cases. (C) 2014 Elsevier B.V. All rights reserved.
引用
收藏
页码:360 / 366
页数:7
相关论文
共 50 条
  • [21] Chemical interactions of silver metal aerosols and iodine compounds in a pressurized water reactor during a severe accident
    Serra, D
    Saint-Raymond, O
    Montanelli, T
    Zoulalian, A
    PROCEEDINGS OF THE 14TH FRENCH CONGRESS ON AEROSOLS CFA 98, 1998, : 205 - 210
  • [22] Study on the influence of source term release on accident consequences in severe accidents for small pressurized water reactor
    Mao, Zhangliang
    Chen, Yuqing
    Wang, Wei
    Cai, Qi
    PROGRESS IN NUCLEAR ENERGY, 2022, 154
  • [23] Reactor Safety Gap Evaluation of Accident-Tolerant Components and Severe Accident Analysis
    Farmer, M. T.
    Bunt, R.
    Corradini, M.
    Ellison, P.
    Francis, M.
    Gabor, J.
    Gauntt, R.
    Henry, C.
    Linthicum, R.
    Luangdilok, W.
    Lutz, R.
    Paik, C.
    Plys, M.
    Rabiti, C.
    Rempe, J.
    Robb, K.
    Wachowiak, R.
    NUCLEAR SCIENCE AND ENGINEERING, 2016, 184 (03) : 293 - 304
  • [24] Analysis on hydrogen risk mitigation in severe accidents for Pressurized Heavy Water Reactor
    Tong, Lili
    Zou, Jie
    Cao, Xuewu
    PROGRESS IN NUCLEAR ENERGY, 2015, 80 : 128 - 135
  • [25] Control rod ejection accident simulation and sensitivity analysis of large advanced pressurized water reactor
    Lan B.
    Pan X.
    Yu S.
    Yi Y.
    He Jishu/Nuclear Techniques, 2023, 46 (02):
  • [26] SEVERE ACCIDENT CONTAINMENT LOADS AND POSSIBLE DESIGN CONCEPTS OF FUTURE LARGE PRESSURIZED-WATER REACTORS
    KESSLER, G
    EIBL, J
    NUCLEAR TECHNOLOGY, 1995, 111 (03) : 358 - 368
  • [27] Ab initio calculations and iodine kinetic modeling in the reactor coolant system of a pressurized water reactor in case of severe nuclear accident
    Xerri, Bertrand
    Canneaux, Sebastien
    Louis, Florent
    Trincal, Julien
    Cousin, Frederic
    Badawi, Michael
    Cantrel, Laurent
    COMPUTATIONAL AND THEORETICAL CHEMISTRY, 2012, 990 : 194 - 208
  • [28] ANALYSIS OF A HYPOTHETICAL CORE MELTDOWN ACCIDENT OF A PRESSURIZED-WATER REACTOR
    PEEHS, M
    HASSMANN, K
    HAGEN, S
    SIEMENS FORSCHUNGS-UND ENTWICKLUNGSBERICHTE-SIEMENS RESEARCH AND DEVELOPMENT REPORTS, 1979, 8 (02): : 114 - 121
  • [29] SEVERE ACCIDENT ANALYSIS USING MAAP WITH DETAILED NODALIZATION IN ADVANCED BOILING WATER REACTOR
    Chitose, Hiromasa
    Kamei, Naoya
    Kimura, Ryusuke
    PROCEEDINGS OF THE 25TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, 2017, VOL 7, 2017,
  • [30] APPROACH FOR THE ANALYSIS OF A SHUTDOWN SCENARIO IN THE FRAMEWORK OF THE VALIDATION OF SEVERE ACCIDENT MANAGEMENT GUIDELINES IN BELGIUM
    Cipollaro, Antonio
    Sallus, Laurent
    PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, : 563 - 573