Comparative analysis of core life-time for the NIRR-1 HEU and LEU cores

Simon, J.; Ibrahim, Y.V.; Adeyemo, D.J.; Garba, Nuraddeen Nasiru; Asuku, Abdulsamad

doi:10.1016/j.pnucene.2021.103970

Cited by 6 publications

(2 citation statements)

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“…Since then, a worldwide effort has been made to restrict, and nally eradicate, the civil use of HEU (Travelli, 1993).Through use of High Enriched Uranium (HEU) to fuel research reactors instantly creates a slew of inescapable and obvious proliferation risks associated with material diversion and/or theft. Thus according sources, the US Department of Energy (DOE) established the Reduced Enrichment for Research and Test Reactors (RERTR) program in 1978 in response to rising concerns about proliferation and the ease with which state and nonstate actors may get nuclear weapons (Ibikunle et al, 2018, Feiveson et al, 2014and Simon et al, 2021. A miniature neutron source reactor (MNSR) is one of numerous research reactors worldwide that use HEU as fuel.…”

Section: Introductionmentioning

confidence: 99%

“…At the start of each operational cycle, the maximum allowable excess reactivity is 4 mk (Fig. 3.1, 3.2 and 3.3, Table 3.1) (Yahaya et al, 2017 andSimon et al, 2021). Previously, a feasibility study was conducted to estimate the enrichment necessary to convert a commercial Miniature Neutron Source Reactor (MNSR) (NIRR-1 in particular) from HEU (90.2%) to LEU (20%) fuel.…”

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: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%