Monte Carlo Calculations of Fast Neutron Transport in Chloride Salts

被引：0

作者：

Stastny, Ondrej ^{[1
]}

Kral, Dusan ^{[1
]}

Stevanka, Kamil ^{[1
]}

Katovsky, Karel ^{[1
]}

Krasa, Antonin ^{[2
]}

机构：

[1] Brno Univ Technol, Dept Elect Power Engn, Brno, Czech Republic

[2] SCK CEN, Inst Adv Nucl Syst, Mol, Belgium

来源：

2020 21ST INTERNATIONAL SCIENTIFIC CONFERENCE ON ELECTRIC POWER ENGINEERING (EPE) | 2020年

关键词：

fast neutron; chloride salt; molten-salt reactors; Monte Carlo; MCNP; nuclear data;

D O I：

暂无

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：

The purpose of this study is to provide data for optimization of an experimental campaign that is under preparation within the frame of the ADAR project (Accelerator Driven Advanced Reactor with molten chloride salt fuel coolant). This article presents results of theoretical investigation of fast neutron field behavior in chloride salt environment. Non-fueled salt coolant (NaCl, KCl, MgCl2) as well as subcritical fuel-containing (PuCl3) one were considered. As an external neutron source, the radio-isotope AmBe source was modelled. Monte Carlo calculations were performed using the MCNP6.2 code with the ENDF/B-VIII.O and JEFF-3.3 nuclear data libraries.

引用

页码：344 / 349

页数：6

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