The effect of graphite thermal column around the newly designed large irradiation channel of GHARR-1 on neutron flux distribution

被引：1
作者：
Asamoah, M. [1 ]
Gyampo, O. [1 ,2 ]
Nyarko, B. J. B. [1 ,2 ]
Akaho, E. H. K. [1 ,2 ]
机构：
[1] Ghana Atom Energy Commiss, Natl Nucl Res Inst, Legon, Accra, Ghana
[2] Univ Ghana, Sch Nucl & Allied Sci, Accra, Ghana
来源：
ANNALS OF NUCLEAR ENERGY | 2012年 / 42卷
关键词：
Neutron; Flux; Thermal column; Graphite; ACTIVATION-ANALYSIS; SAMPLES; REACTOR; GRADIENTS;
D O I：
10.1016/j.anucene.2011.11.019
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：
Monte Carlo N-Particle code (MCNP-5) was employed to simulate the neutron flux profile in a newly designed irradiation site surrounded by a graphite thermal column for Large Sample Neutron Activation Analysis, in the Ghana Research Reactor-1. The results shows that the average thermal neutron flux in the irradiation channel surrounded with 6 cm thick graphite was 5.45 x 10(10) n cm(-2) s(-1) as compared with 1.74 x 10(10) n cm(-2) s(-1) when there is no graphite around the irradiation channel. This shows an increase in the thermal neutron flux in the irradiation channel by a factor of 3.13. The thermal neutron flux gradient decreased at 7.0 x 10(9) n cm(-2) s(-1) per cm to 3.90 x 10(7) n cm(-2) s(-1) per cm when the channel is surrounded by 6 cm thick graphite which makes it very suitable for Large Sample Neutron Activation Analysis. The simulation agrees very well with the experimental k(eff) of 1.00400 as compared with the final k(eff) of 1.00390 recorded by this simulation. (C) 2011 Elsevier Ltd. All rights reserved.
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页码：131 / 134
页数：4
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