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contributor authorSinh Nguyen
contributor authorT.;Wang
contributor authorXiaolin;Bromley
contributor authorBlair P.
date accessioned2022-08-18T13:03:08Z
date available2022-08-18T13:03:08Z
date copyright6/1/2022 12:00:00 AM
date issued2022
identifier issn2332-8983
identifier otherners_008_03_031502.pdf
identifier urihttp://yetl.yabesh.ir/yetl1/handle/yetl/4287342
description abstractThe development of advanced fuels and fuel cycles for conventional Generation III+ reactors, advanced reactors (such as Generation IV), and small modular reactors will help ensure the long-term sustainability and safety of the use of nuclear energy. Thorium-based fuels are an example of an advanced fuel that could augment and extend uranium resources. As part of previous efforts in Canada to investigate the use of thorium-based fuels for potential use in pressure-tube heavy-water reactors and other technologies, irradiation experiments with various thorium-containing fuels had been conducted in the National Research Universal (NRU) reactor at the Chalk River Laboratories. The NRU reactor physics computational tools and methods, developed initially for conventional enriched uranium fuel, had also been extended for analysis of thorium-based fuel experiments, with most satisfactory results. In this study, a number of physics and operation factors have been analyzed to quantify their effects on the production and burnup of 233U in thorium-based fuel, as well as to improve both the analysis and the use of thorium fuels and fuel cycles.
publisherThe American Society of Mechanical Engineers (ASME)
titleReview of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in the National Research Universal Reactor
typeJournal Paper
journal volume8
journal issue3
journal titleJournal of Nuclear Engineering and Radiation Science
identifier doi10.1115/1.4053691
journal fristpage31502-1
journal lastpage31502-12
page12
treeJournal of Nuclear Engineering and Radiation Science:;2022:;volume( 008 ):;issue: 003
contenttypeFulltext


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