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

M. Asamoah; O. Gyampo; B. J.B. Nyarko; E. H.K. Akaho

doi:10.1016/j.anucene.2011.11.019

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

M. Asamoah, O. Gyampo, B. J.B. Nyarko, E. H.K. Akaho

Research output: Contribution to journal › Article › peer-review

3 Citations (Scopus)

Abstract

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 × 10 ¹⁰ n cm ^-2 s ^-1 as compared with 1.74 × 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 × 10 ⁹ n cm ^-2 s ^-1 per cm to 3.90 × 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.

Original language	English
Pages (from-to)	131-134
Number of pages	4
Journal	Annals of Nuclear Energy
Volume	42
DOIs	https://doi.org/10.1016/j.anucene.2011.11.019
Publication status	Published - Apr 2012
Externally published	Yes

Keywords

Flux
Graphite
Neutron
Thermal column

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10.1016/j.anucene.2011.11.019

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

abstract = "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 × 10 10 n cm -2 s -1 as compared with 1.74 × 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 × 10 9 n cm -2 s -1 per cm to 3.90 × 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.",

keywords = "Flux, Graphite, Neutron, Thermal column",

author = "M. Asamoah and O. Gyampo and Nyarko, {B. J.B.} and Akaho, {E. H.K.}",

year = "2012",

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doi = "10.1016/j.anucene.2011.11.019",

language = "English",

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journal = "Annals of Nuclear Energy",

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T1 - The effect of graphite thermal column around the newly designed large irradiation channel of GHARR-1 on neutron flux distribution

AU - Asamoah, M.

AU - Gyampo, O.

AU - Nyarko, B. J.B.

AU - Akaho, E. H.K.

PY - 2012/4

Y1 - 2012/4

N2 - 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 × 10 10 n cm -2 s -1 as compared with 1.74 × 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 × 10 9 n cm -2 s -1 per cm to 3.90 × 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.

AB - 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 × 10 10 n cm -2 s -1 as compared with 1.74 × 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 × 10 9 n cm -2 s -1 per cm to 3.90 × 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.

KW - Flux

KW - Graphite

KW - Neutron

KW - Thermal column

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DO - 10.1016/j.anucene.2011.11.019

M3 - Article

AN - SCOPUS:84856950733

SN - 0306-4549

VL - 42

SP - 131

EP - 134

JO - Annals of Nuclear Energy

JF - Annals of Nuclear Energy

ER -

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

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Keywords

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