High Temperature Gas-Cooled Test Reactor Point Design: Summary Report

Sterbentz, James W.; Bayless, Paul D.; Nelson, Lee O.; Gougar, Hans D.; Kinsey, James C.; Strydom, Gerhard

doi:10.2172/1260453

Cited by 4 publications

(2 citation statements)

References 2 publications

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“…In this work, the geometry used to model a graphite core component is based on reports that analyze prismatic blocks [1], [2]. The full geometry that we are using as baseline is shown in Figure 2, after [2]. We generated both the geometry and the finite element mesh using Trelis, a meshing preprocessor based on Sandia National Laboratory's CUBIT mesher.…”

Section: Geometrymentioning

confidence: 99%

Preliminary design analysis workflow for Division 5 HHA-3200 requirements for graphite core components

Nicolas

Messner

Sham

2020

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This report presents a design analysis workflow for graphite core components and assemblies, based on the design rules of ASME Boiler Pressure and Vessel Code, Section III, Division 5, Article HHA-3000. The workflow contains three stages: developing the design of the graphite core component, modeling the component with the finite element software MOOSE, and assessing if the component passes/fails the criteria of the HHA-3000 design rules. Since the design rules use probabilistic metrics specifically established to evaluate brittle materials, we developed a python library that performs all the statistical calculations necessary for the evaluations of the HHA-3000 criteria.

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Section: Geometrymentioning

confidence: 99%

Preliminary design analysis workflow for Division 5 HHA-3200 requirements for graphite core components

Nicolas

Messner

Sham

2020

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“…Appendix B contains descriptions of the reactor physics and thermal-hydraulics computer models used in the analyses. Descriptions of earlier scoping analyses that led to this core configuration are provided in Appendix C. Sterbentz et al (2016) provides a summarized version of the information presented in this report, focusing on the final core design configuration.…”

Section: Introductionmentioning

confidence: 99%

High-Temperature Gas-Cooled Test Reactor Point Design

Sterbentz¹,

Bayless²,

Nelson³

et al. 2016

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A point design has been developed for a 200-MW, high-temperature, gascooled test reactor. The point design concept uses standard prismatic blocks and 15.5% enriched uranium oxycarbide fuel. Reactor physics and thermal-hydraulics simulations have been performed to characterize the capabilities of the design. In addition to the technical data, overviews are provided on the technological readiness level, licensing approach, and costs. vi vii The HTGTR aligns with the NRC's definition of a Test Facility, as found in 10 CFR 50.2. Test reactors are one of the non-power reactors that the NRC licenses under the authority of Subsection 104c x of the Atomic Energy Act and issues "Class 104c" licenses. Congress directed the NRC to impose the minimum amount of regulation on Subsection 104(c) research reactor and test reactor licensees. In keeping with this direction, the NRC staff utilizes NUREG-1537 as the primary guidance for review of research reactors and test reactor technologies and license applications. DOE and NRC established a joint initiative in July 2013 to develop guidance for advanced reactor developers and other stakeholders on how the existing general design criteria reflected in 10 CFR 50, Appendix A, can be adapted to non-LWRs. A proposed set of general design criteria adaptations specific to modular HTGRs was developed by a DOE/national laboratory team and submitted to NRC for review in December 2014. A self-assessment has been performed on the HTGTR scoring against the DOE-developed criteria.

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