Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP-Reference-Cited by-同舟云学术

Design of boron carbide-shielded irradiation channel of the outer irradiation channel of the Ghana Research Reactor-1 using MCNP

Published:2011-01 Issue:1 Volume:69 Page:85-89
ISSN:0969-8043
Container-title:Applied Radiation and Isotopes
language:en
Short-container-title:Applied Radiation and Isotopes

Author:

Abrefah R.G.,Sogbadji R.B.M,Ampomah-Amoako E.,Birikorang S.A.,Odoi H.C.,Nyarko B.J.B

Publisher

Elsevier BV

Subject

Radiation

Reference7 articles.

1. Anim-Sampong, S., 2002. Progress Report on ICTP TRIL Fellowship Training, ICTP-TRIL/ENEA/GAEC/PR/01/02.

2. Anim-Sampong, S., 2001. Three-dimensional Monte Carlo Modeling and particle transport simulation of the Ghana Research Reactor-1. Technical report, NNRI/GAEC/ICTP/ENEA-TR.01/2001.

3. Anim-Sampong, S., 2006. Progress Report, ANL RERTR Visiting Scholar (Research Fellow) ANL, USA.

4. Briesmeister, J.F. (Ed.), 2000. MCNPTM – A General Monte Carlo N-particle transport code. Version 4c. LA-13709-M.

5. General description of the Ghana MNSR, MNSR Training Material;Gao Jijin,1993

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