The use of WIMS and CITATION codes in fuel loading required for the conversion of HEU MNSR core to LEU

Azande, T.S.; Balogun, G.I.; Ajuji, A.S.; Jonah, S.A.; Ahmed, Y.A.

doi:10.1016/j.anucene.2010.04.013

Cited by 6 publications

(3 citation statements)

References 7 publications

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“…U-238, on the other hand, is only ssionable beyond threshold energy of roughly 1MeV. Below this threshold energy, neutron capture dominates this isotope's overall absorption cross section (Glaser, 2005 andAzande et al, 2010). Uranium enriched to at least 90% U-235 has been used to build nuclear bombs, and uranium with this level of enrichment is known as highly enriched uranium (HEU).…”

Section: High Enriched Uranium (Heu) and Low Enriched Uranium (Leu)mentioning

confidence: 99%

“…A miniature neutron source reactor (MNSR) is one of numerous research reactors worldwide that use HEU as fuel. The Nigerian Research Reactor-1 (NIRR-1) is classi ed as a HEU because it is 90% enriched in ssile U-235 (Azande et al, 2010). It was created primarily for neutron activation analysis (NAA) and minimal radioisotope generation (Jonah et al, 2013).…”

Section: Introductionmentioning

confidence: 99%

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Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Balami

2022

Preprint

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The core of the Nigeria Research Reactor-1 has been converted from Highly Enriched Uranium (HEU) fuel to Low Enriched Uranium (LEU); nevertheless, a core lifetime analysis of the converted HEU and current LEU fuel is required. The core lifetime analysis of the NIRR-1 converted HEU and current LEU cores was carried out using the Winfrith Improved Multigroup Scheme-Argonne National Laboratory (WIMS-ANL) and Reactor BUrnup System-Argonne National Laboratory computer codes in this work (REBUS-ANL). One group cross section was generated using the WIMS-ANL. For core lifetime analysis, these group cross sections were employed in the REBUS-ANL programme. A simple reactivity rundown was performed to estimate the core lifetime for HEU and LEU cores at two power levels using the REBUS-ANL code (full and half power). The lifetime of the LEU core was predicted to be approximately 11.91 percent longer than that of the HEU core at full power and 11.81 percent at half power based on the results obtained. This is in good agreement with the value 11 percent reported in the literature, indicating that the selected LEU core can be operated for a longer period of time than the HEU core.

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Section: High Enriched Uranium (Heu) and Low Enriched Uranium (Leu)mentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Balami

2022

Preprint

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“…Any deviation noted in the solutions of point kinetic parameters is a result of the sudden change in flux shape (Jonah et al, 2012;Azande, 2011, Ibrahim, 2015. Similarly, when the neutron source transient trip data was over predicted for negative insertion, it would lead to wrong results in point kinetic parameters (Bergenas and Scheinman, 2008;Azande et al, 2010).…”

Section: Introductionmentioning

confidence: 99%

Serpent Code Point Kinetic Parameters Analysis: A Nexus for Nigeria Research Reactor – 1 Core Conversion Using Enriched Uranium Dioxide Fuel

Abubakar¹,

Ismaila²,

Yamusa³

2022

FJS

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The International Atomic Energy Agency (IAEA) requires that all test and research reactors operating on Higher Enriched Uranium (HEU) should be converted to Low Enriched Uranium (LEU) for safety and security purposes. Nigeria having a Miniature Neutron Source Reactor (MNSR) has been long interested in fuel technological research not just to develop the area but also to meet with resolution on the nuclear treaty set out by the global nuclear regulatory body. In this study, reactor kinetic parameters such as effective delayed neutron fractions, prompt neutron lifetime as well as mean neutron generation time were analysed for Nigerian Research Reactor-1 (NIRR-1). Serpent Monte Carlo code 1.17 is used in the analysis. For delayed neutron parameters determination, we used fission probability iteration under one averaged generation time and neutron population rate.The calculated values for delayed neutron were recorded as analogue prompt and implicit prompt neutron lifetime, reproduction time and emission time are in the order of 3×10-7 (s), in agreement with the calculated data from the nuclear data libraries and some literature.The result for delay neutron fraction and other time-based parameters support the fuel core conversion for NIRR-1.The computational and pictorial results obtained from Serpent code simulation described well the transient behavior of the delayed neutron in this reactor.The analytical results also spelled out the relevance and compatibility of low enriched uranium dioxide fuel over higher enriched type.The result of this study conforms with other results obtained from similar reactors but with different Monte Carlo codes and with higher enriched uranium

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Analysis of core life-time and neutronic parameters for HEU and potential LEU/MEU fuels in a typical MNSR

Nawaz

Mirza

et al. 2012

Annals of Nuclear Energy

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The use of WIMS and CITATION codes in fuel loading required for the conversion of HEU MNSR core to LEU

Cited by 6 publications

References 7 publications

Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Nigerian Research Reactor-1 (NIRR-1) Core Life-time Analysis using Winfrith Improved Multigroup Scheme-Argonne National Lab (WIMS-ANL) and REactor BUrnup System-Argonne National Lab (REBUS-ANL) Computer Code

Serpent Code Point Kinetic Parameters Analysis: A Nexus for Nigeria Research Reactor – 1 Core Conversion Using Enriched Uranium Dioxide Fuel

Analysis of core life-time and neutronic parameters for HEU and potential LEU/MEU fuels in a typical MNSR

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