HTGR experience, programs, and future applications

Moore, Roger A.; Kantor, M.E.; Brey, H.L.; Olson, H.G.

doi:10.1016/0029-5493(82)90212-6

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Applicability To Htgr or Other Gas Cooled Designs1

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2021

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Cited by 13 publications

(1 citation statement)

References 8 publications

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“…High Temperature Gas-Cooled Reactors, (HTGRs) [71] are reactor designs using TRISO [72] particle fuel in a graphite matrix and helium gas as the coolant. Both prismatic fuel block [73] and pebble bed fueled designs exist.…”

Section: Applicability To Htgr or Other Gas Cooled Designsmentioning

confidence: 99%

Spatial power profiling method using visual information in reactors with optically transparent coolants

Hearne

Tsvetkov

2020

Annals of Nuclear Energy

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Section: Applicability To Htgr or Other Gas Cooled Designsmentioning

confidence: 99%

Spatial power profiling method using visual information in reactors with optically transparent coolants

Hearne

Tsvetkov

2020

Annals of Nuclear Energy

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Development of HTR Technology

Kugeler

Zhang

2018

Modular High-Temperature Gas-Cooled Reactor Power Plant

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Design and analysis of concrete reactor vessels: New developments, problems and trends

Bažant

1984

Nuclear Engineering and Design

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This lecture reviews new developments in analysis and design of prestressed concrete reactor vessels (PCRV). After a brief assessment of the current status and experience, the advantages, disadvantages, and especially the safety features of PCRV, are discussed. Attention is then focused on the design of penetrations and openings, and on the design for high-temperature resistance -areas in which further developments are needed. Various possible designs for high-temperature exposure of concrete in a hypothetical accident are analyzed. Considered are not only PCRVs for gas-cooled reactors (GCR), but also guard vessels for liquid metal fast breeder reactors (LMFBR), for which designs mitigating the adverse effects of molten sodium, molten steel, and core melt are surveyed. Realistic analysis of these problems requires further development in the knowledge of material behavior and its mathematical modeling. Recent advances in the modeling of high-temperature response of concrete, including pore water transfer, pore pressure, creep and shrinkage are outlined. This is followed by a discussion of new developments in the analysis of cracking of concrete, where the need of switching from stress criteria to energy criteria for fracture is emphasized. The lecture concludes with a brief discussion of long-time behavior, the effect of aging, and probabilistic analysis of creep.

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HTGR experience, programs, and future applications

Cited by 13 publications

References 8 publications

Spatial power profiling method using visual information in reactors with optically transparent coolants

Spatial power profiling method using visual information in reactors with optically transparent coolants

Development of HTR Technology

Design and analysis of concrete reactor vessels: New developments, problems and trends

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