Neutronic evaluations for MNSR research reactor core conversion from HEU to LEU

被引：3

作者：

Abtin, F. ^{[2
]}

Feghhi, S. A. H. ^{[1
]}

Jafarikia, S. ^{[1
]}

机构：

[1] Shahid Beheshti Univ, Dept Radiat Applicat, Tehran, Iran

[2] Nucl Sci & Technol Res Inst, Tehran, Iran

来源：

ANNALS OF NUCLEAR ENERGY | 2013年 / 51卷

关键词：

MNSR; Core conversion; Neutronic calculations; High density fuels; SYSTEM; CODE;

D O I：

10.1016/j.anucene.2012.08.016

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：

We studied enrichment reduction evaluations for Iranian Miniature Neutron Source Reactor (MNSR) preserving prior reactivity limitations. Utilization of high density Low Enriched Uranium (LEU) fuels such as UO2. U3Si2 and U9Mo have been addressed from neutronics point of view. The Monte Carlo code MCNP4C has been used for studying the reactor core neutronic parameters. The feasibility of candidate LEU fuels have been validated via the MNSR reference fuel parameters. The results show that the average neutron flux in irradiation channels of LEU core configurations is reduce within 7%. According to the calculated reactivity parameters and thermal neutron flux in irradiation channels, this reduction would not affect the reactor safety as well as its applicability. (C) 2012 Elsevier Ltd. All rights reserved.

引用

页码：69 / 73

页数：5

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