Nuclear design

Fujimoto, Nozomu; Nojiri, Naoki; Ando, Hiroei; Yamashita, Kiyonobu

doi:10.1016/j.nucengdes.2004.07.008

Cited by 14 publications

(3 citation statements)

References 3 publications

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“…Multiple vendors have initiated the CNSC prelicensing review process with such a design [2,12,13]. When certain specifics of the SMR designs were undefined or otherwise not available, features of the generic Areva HTGR concept [14,15] or the HTTR [16,17] were assumed. The key features of the generic HTGR-type SMR include:…”

Section: Assumed Accident Scenariomentioning

confidence: 99%

Results of a Phenomena Identification and Ranking Table (Pirt) Exercise for a Severe Accident in a Small Modular High-Temperature Gas-Cooled Reactor

et al. 2019

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Canada has attracted specific interest from developers of nonwater-cooled small modular reactor (SMR) technologies, including concepts based on high-temperature gas-cooled reactors (HTGRs). It is anticipated that some research and development (R&D) will be necessary to support safety analysis and licensing of these reactors in Canada. The Phenomena Identification and Ranking Table (PIRT) process is a formalized method in which a panel of experts identifies which physical phenomena are most relevant to the reactor safety analysis and how well understood these phenomena are. The PIRT process is thus a tool to assess current knowledge levels and (or) predictive capabilities of models, thus providing direction to a focused R&D program. This paper summarizes the results of a PIRT process performed by a panel of experts at Canadian Nuclear Laboratories for a limiting or “worst-case” accident scenario at a generic HTGR-type SMR. Suggestions are given regarding the highest priority R&D items to support severe accidents analysis of these reactors.

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Section: Assumed Accident Scenariomentioning

confidence: 99%

Results of a Phenomena Identification and Ranking Table (Pirt) Exercise for a Severe Accident in a Small Modular High-Temperature Gas-Cooled Reactor

et al. 2019

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“…4. The RPV has a top head which includes standpipes, a top head dome, a top head flange, thermal shields, etc., and a RPV body comprised of a shell flange, shell, three standpipes, a bottom head petal, skirt, a bottom head dome, a support ring, and radial keys.…”

Section: Reactor Pressure Vesselmentioning

confidence: 99%

Evaluation of the Start-Up Core Physics Tests at Japan's High Temperature Engineering Test Reactor (Fully-Loaded Core)

Bess

2009

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“…Nevertheless, optimization methods often are not thoroughly described, a brute force approach is applied, or a comprehensive trial and error process is followed (e.g. Cole and Bonin, 2007;Fujimoto et al, 2004;Munkhbat and Obara, 2013;Paquette and Bonin, 2011;Kloosterman et al, 2001;Patel and Tsvetkov, 2013). An iterative response-driven design process is sometimes followed (e.g.…”

Section: Introductionmentioning

confidence: 99%