Experimental Investigations of Heat Transfer Upon Sodium Boiling in a Model Fuel Assembly for Safety Validation of an Advanced Fast Reactor

被引：1

作者：

Khafizov, R. R. ^{[1
]}

Rachkov, V. I. ^{[1
]}

Poplavskii, V. M. ^{[1
]}

Sorokin, A. P. ^{[1
]}

Ashurko, Yu M. ^{[1
]}

Volkov, A. V. ^{[1
]}

Ivanov, E. F. ^{[1
]}

Privezentsev, V. V. ^{[1
]}

机构：

[1] Leipunskii Inst Phys & Power Engn GNTs RF FEI, State Sci Ctr Russian Federat, Obninsk, Russia

来源：

ATOMIC ENERGY | 2016年 / 120卷 / 05期

关键词：

11;

D O I：

10.1007/s10512-016-0139-2

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：

A structural concept using a sodium cavity located above the core of a reactor is proposed as a means of preventing accidents resulting in the destruction of core elements. The experimental investigations of heat transfer performed on the AR-1 stand with boiling of sodium in a model fuel assembly of a fast reactor with a sodium cavity above the core in a regime with natural circulation have shown that long-time cooling of fuel assemblies is possible. The data obtained are used to refine the computational model of sodium boiling in fuel assemblies and to verify the COREMELT computational code.

引用

页码：328 / 334

页数：7

共 40 条

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