Core geometry for recriticality prevention against CDA in sodium-cooled fast reactor

被引：2

作者：

Suetomi, Eiichi ^{[1
]}

Nakano, Satoshi ^{[1
]}

Takezawa, Hiroki ^{[1
]}

Takaki, Naoyuki ^{[1
]}

机构：

[1] Tokyo City Univ, Dept Nucl Safety Engn, Setagaya Ku, 1-28-1 Tamazutsumi, Tokyo 1588557, Japan

来源：

SPECIAL ISSUE OF FOR THE FIFTH INTERNATIONAL SYMPOSIUM ON INNOVATIVE NUCLEAR ENERGY SYSTEMS | 2017年 / 131卷

关键词：

Sodium-cooled fast reactor; CDA; Recriticality prevention; Core geometry; Reactor physics;

D O I：

10.1016/j.egypro.2017.09.444

中图分类号：

TE [石油、天然气工业]; TK [能源与动力工程];

学科分类号：

0807 ; 0820 ;

摘要：

In core disruptive accident (CDA) of sodium-cooled fast reactors (SFRs), fuel and steel can melt to form a molten pool. The objective of the present work is to investigate design measures for core of SFR to prevent recriticality. This paper studied core geometry of convex cross-section shape to increase neutron leakage from core surface in case of core compaction. In order to evaluate effective neutron multiplication factor, 70-group neutron diffusion calculations were performed by changing parameters related to the convex core geometry (i.e. ratio of inner height to inner diameter). Neutron diffusion code and nuclear data library employed in those calculations are CITATION and JENDL-3.3, respectively. By optimizing core configuration, the compaction reactivity of the convex shaped core showed drastic reduction from 2.07 % of reference cylindrical core (Japan Sodium-cooled Fast Reactor) to -3.28 %. (C) 2017 The Authors. Published by Elsevier Ltd.

引用

页码：45 / 52

页数：8

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