Severe accident;
Debris bed coolability;
Coupled analysis;
MELCOR;
COCOMO;
2-PHASE FLOW;
COOLABILITY;
DRYOUT;
WATER;
VALIDATION;
PRESSURE;
MELCOR;
CODE;
D O I:
10.1016/j.anucene.2021.108643
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 cornerstone of severe accident strategy of Nordic BWRs is to flood the reactor cavity for the long-term coolability of an ex-vessel debris bed. As a prerequisite of the long-term coolability, the hot debris bed formed from fuel coolant interactions (FCI) should be quenched. In the present study, coupling of the MELCOR and COCOMO codes is realized with the aim to analyze the quench process of an ex-vessel debris bed under prototypical condition of a Nordic BWR. In this coupled simulation, MELCOR performs an integral analysis of accident progression, and COCOMO performs the thermal-hydraulic analysis of the debris bed in the flooded cavity. The effective diameter of the particles is investigated. The discussion on the bed's shape shows a significant effect on the propagation of the quench front, due to different flow patterns. Compared with MELCOR standalone simulation, the coupled simulation predicts earlier cavity pool saturation and containment venting. (c) 2021 The Authors. Published by Elsevier Ltd. This is an open access article under the CC BY license (http:// creativecommons.org/licenses/by/4.0/).
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden
Basso, S.
Konovalenko, A.
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机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden
Chen, Yangli
Ma, Weimin
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机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden
机构:
Cadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, FranceCadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, France
Chikhi, Nourdine
Fichot, F.
论文数: 0引用数: 0
h-index: 0
机构:
Cadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, FranceCadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, France
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden
Basso, S.
Konovalenko, A.
论文数: 0引用数: 0
h-index: 0
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21,D5, S-10691 Stockholm, Sweden
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden
Chen, Yangli
Ma, Weimin
论文数: 0引用数: 0
h-index: 0
机构:
Royal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, SwedenRoyal Inst Technol KTH, Div Nucl Power Safety, Roslagstullsbacken 21, S-10691 Stockholm, Sweden
机构:
Cadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, FranceCadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, France
Chikhi, Nourdine
Fichot, F.
论文数: 0引用数: 0
h-index: 0
机构:
Cadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, FranceCadarache Nucl Ctr, IRSN French Nucl Safety Inst, BP 3, F-13115 St Paul Les Durance, France