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Irradiation Experiment Design Parameters for NBSR Fuel Conversion (Technical Report) | OSTI.GOV

機(jī)譯：NBsR燃料轉(zhuǎn)換的輻照實(shí)驗(yàn)設(shè)計(jì)參數(shù)（技術(shù)報(bào)告）| OsTI.GOV

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It has been proposed to convert the National Institute of Standards and Technology research reactor, known as the NBSR, from high-enriched uranium (HEU) fuel to low-enriched uranium (LEU) fuel. The motivation to convert the NBSR to LEU fuel is to reduce the risk of proliferation of special nuclear material. This report is a compilation of relevant information from recent studies related to the proposed conversion using a metal alloy of LEU with 10 w/o molybdenum. The objective is to inform the design of irradiation experiments that are being planned. This report provides relevant dimensions of the fuel elements, and average and maximum fission rate densities and fission densities. The latter profiles are given for different plates to show the variation throughout the core. A summary of the methodology to obtain these results is presented. Fuel element tolerance assumptions and hot channel factors used in the safety analysis are also given.

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  • 年(卷),期 2000(),
  • 年度 2000
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  • 總頁(yè)數(shù) 54
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