Thermo-chemical behavior of PHWR disassembled channel during severe accident condition: Numerical and experimental investigation

被引:4
|
作者
Kumar, Rohit [1 ]
Mishra, Manish [1 ]
Gokhale, Onkar [2 ]
Mukhopadhyay, D. [2 ]
机构
[1] Indian Inst Technol Roorkee, Dept Mech & Ind Engn, Roorkee 247667, Uttar Pradesh, India
[2] Bhabha Atom Res Ctr, Reactor Safety Div, Mumbai, Maharashtra, India
关键词
Severe core damage accident; Channel disassembly; Steam ingression; Thermo-chemical reaction; Hydrogen generation; CONVECTION HEAT-TRANSFER; NATURAL-CONVECTION; PRESSURE TUBE; INDIAN PHWR; EQUATIONS;
D O I
10.1016/j.anucene.2021.108733
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 postulated severe core damage accidents in PHWR can get initiated from limited core damage accidents incase moderator cooling is lost. Excessive sagging of the exposed fuel channels from moderator boil-off leads to channel disassembly. Steam reacts with fresh zircaloy at higher temperatures and generates hydrogen to a large extent. The present work investigates the effect of ingression of steam and associated hydrogen generation on a simulated disassembled channel for 220 MW(e) PHWR under postulated severe core damage accident conditions. The assessment of steam ingression in the disassembled channel at various inclination angles is carried out. The study shows that the inclination angle highly influences the ingression of steam, fuel channel temperature and hydrogen generation. The very low steam ingression for horizontal position of the channel was found to limit the Zr oxidation, while at higher inclinations angle, sufficient amount of steam ingression leads to higher hydrogen generation. (c) 2021 Elsevier Ltd. All rights reserved.
引用
收藏
页数:14
相关论文
共 50 条
  • [21] Experimental study on the fuel behavior during reactivity accident at power operation condition
    Katanishi, S
    Ishijima, K
    JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, 1995, 32 (11) : 1098 - 1107
  • [22] Experimental investigation and thermo-chemical modeling of methane pyrolysis in a liquid metal bubble column reactor with a packed bed
    Geissler, T.
    Plevan, M.
    Abanades, A.
    Heinzel, A.
    Mehravaran, K.
    Rathnam, R. K.
    Rubbia, C.
    Salmieri, D.
    Stoppel, L.
    Stueckrad, S.
    Weisenburger, A.
    Wenninger, H.
    Wetzel, Th.
    INTERNATIONAL JOURNAL OF HYDROGEN ENERGY, 2015, 40 (41) : 14134 - 14146
  • [23] An investigation on the physical and chemical behaviors of fuel debris during severe accident progression
    Song, Jinho
    Min, BeogTae
    Hong, SeongWan
    An, SangMo
    Hong, SeongHo
    PROGRESS IN NUCLEAR ENERGY, 2018, 106 : 345 - 356
  • [24] Experimental investigation of temperature and heat distribution across 220 MWe Indian PHWR channel under boil-off condition
    Yadav, Subodh Kumar
    Kumar, Ravi
    Mukhopadhyay, D.
    Majumdar, Prasanna
    ANNALS OF NUCLEAR ENERGY, 2020, 145
  • [25] Experimental study on thermo-chemical phenomena during interaction of limestone concrete with liquid sodium under inert atmosphere
    Das, Sanjay Kumar
    Sharma, Anil Kumar
    Parida, F. C.
    Kasinathan, N.
    CONSTRUCTION AND BUILDING MATERIALS, 2009, 23 (11) : 3375 - 3381
  • [26] Experimental Research on Mechanism of Aerosol Re-entrainment Behavior in Containment under Severe Accident Condition
    Hu Z.
    Chen L.
    Ji S.
    Wei Y.
    Shi X.
    Zheng G.
    Hedongli Gongcheng/Nuclear Power Engineering, 2023, 44 (04): : 253 - 258
  • [27] THE BEHAVIOR OF IMPURITIES DURING PRODUCER GAS IMPLEMENTATION AS ALTERNATIVE FUEL IN STEEL REHEATING FURNACES: A CFD AND THERMO-CHEMICAL STUDY
    Pour, M. Saffari
    Andersson, N. A. I.
    Ersson, M.
    Jonsson, L. T. I.
    Niska, J.
    Rensgard, A.
    Jonsson, P. G.
    PROCEEDINGS OF THE ASME INTERNATIONAL MECHANICAL ENGINEERING CONGRESS AND EXPOSITION, 2016, VOL. 6A, 2017,
  • [28] Experimental and numerical investigation of thermo-hydraulic behavior in a rotating wedge-shaped trailing edge channel with internal jet impingement
    Yan, Kaixin
    Deng, Hongwu
    Li, Hua
    APPLIED THERMAL ENGINEERING, 2023, 234
  • [29] CFD investigation of PWR channel shapes effects during rolling motion under normal and accident condition
    Movaffagh, M.
    Abbasi, M.
    Zolfaghari, A.
    ANNALS OF NUCLEAR ENERGY, 2023, 181
  • [30] NUMERICAL SIMULATION OF THE BEHAVIOR OF FISSION PRODUCTS IN THE PRIMARY CIRCUIT OF THE VVER DURING THE LOCA SEVERE ACCIDENT
    Tsaun, S. V.
    Bezlepkin, V. V.
    Kiselev, A. E.
    Potapov, I. A.
    Strizhov, V. F.
    Zaichik, L. I.
    PROCEEDINGS OF THE 17TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING, VOL 2, 2009, : 361 - 367