Automating some analysis and design calculations of miniature neutron source reactors at CERT (I)-Reference-Cited by-同舟云学术

Automating some analysis and design calculations of miniature neutron source reactors at CERT (I)

Published:2003-01 Issue:1 Volume:30 Page:81-92
ISSN:0306-4549
Container-title:Annals of Nuclear Energy
language:en
Short-container-title:Annals of Nuclear Energy

Author:

Balogun G.I

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering

Reference5 articles.

1. Balogun, G.I., Garbe, H.B., Umar, T.M., Oladipo, M.O.A., Egun, P.M., Ewa, I.O.B., et al. Nigerian research reactor-1 safety analysis report. CERT/NIRR-1/001, Zaria, 1999. p. 37–59.

2. Fowler, T.B., Vondy, D.R., Cunningham, G.M. Nuclear reactor analysis code CITATION. ORNL-TM-2496, 1989.

3. Hansall, M.J., 1980. A summary of WIMSD4 input options. UKAEA, AEEW-M 1327, 1980.

4. Qazi MK. Neutronic analysis and reactivity coefficient calculations for Pakistan Research Reactor-2. PINSTECH-123, 1991.

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