World Journal of Nuclear Science and Technology

World Journal of Nuclear Science and Technology

ISSN Print: 2161-6795
ISSN Online: 2161-6809
www.scirp.org/journal/wjnst
E-mail: wjnst@scirp.org
"Study of Criticality Safety and Neutronic Performance for a 348-Fuel-Pin Ghana Research Reactor-1 LEU Core Using MCNP Code"
written by Henry Cecil Odoi, Edward H. K. Akaho, Sunday A. Jonah, Rex Gyeabour Abrefah, Viva Y. Ibrahim,
published by World Journal of Nuclear Science and Technology, Vol.4 No.1, 2014
has been cited by the following article(s):
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[1] Assessment of Axial Power Peaking Factors in GHARR-1 LEU Core: A Decadal Simulation Analysis
Amoako, RG Abrefah… - World Journal of Nuclear …, 2023
[2] Transient Studies on Low-Enriched-Uranium Core of Ghana Research Reactor–1 (GHARR-1)
2020
[3] Steady State Safety Analysis of Ghana Research Reactor− 1 (GHARR-1) with LEU Core
2020
[4] Steady-State Safety Analysis of Ghana Research Reactor-1 With Low-Enriched-Uranium Core
2020
[5] Thermal Hydraulic Analysis of Low Enriched Uranium (LEU) Core of the Ghana Research Reactor-1 (GHARR-1)
2019
[6] Methodologies for Evaluating Security Risk and Safeguards for HEU to LEU conversion of a Miniature Neutron Source Reactor (MNSR) using SCALE and ORIGEN
2018
[7] Verification of SuperMC for MNSRs core analysis: The case of Ghana Research Reactor-I
Annals of Nuclear Energy, 2018
[8] Analysis of specific design aspects of a thorium-uranium fuelled European Pressurised Reactor
2017
[9] Intra-Party Conflicts And The Prospects Of Democratic Consolidation In Ghana's Fourth Republic: A Comparative Study Of The New Patriotic Party (NPP) And The …
2017
[10] Comparison of Neutronic Safety Parameters of Some Commercial Pwrs under Consideration for Ghana's First Nuclear Power Plant
2017
[11] Study of criticality safety and neutronic parameters of UO2 fuel in MTR research reactors using the MCNP4C code
Annals of Nuclear Energy, 2016
[12] Study of criticality safety and neutronic parameters of UO 2 fuel in MTR research reactors using the MCNP4C code
Annals of Nuclear Energy, 2016
[13] Prompt neutron lifetime calculations for the NIRR-1 reactor
2015
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