Gas-Cooled Nuclear Power Reactors

Agnew, Harold M.

doi:10.1038/scientificamerican0681-55

Cited by 24 publications

(5 citation statements)

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“…This is the concept that has been developed over many years by General Atomics (GA) as the MHTGR and more recently the direct-cycle gas-turbine modularhelium reactor (GT-MHR). A Scientific American article by Harold Agnew (Agnew 1981) discussed these early monolithic HTGR reactor designs.…”

Section: D1-312 Basic Information From 2009 Afc-cbdmentioning

confidence: 99%

Advanced Fuel Cycle – Cost Basis Report: Module D1-3 Uranium-based Ceramic Particle Fuel Fabrication

Williams,

Hansen,

Hoffman

2021

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Module D1-3 Uranium-Based Ceramic Particle Fuel Fabrication INL/EXT-21-64514 (September 2021) D1-3-iii Advanced Fuel Cycle Cost Basis REVISION LOG Rev. Date Affected Pages Revision Description 2004 Version of AFC-CBR in which this module first appeared: 2004 as Module D1-3 2021 All Latest version of module in which new technical data was used to establish unit cost ranges: 2021 New technical/cost data which have recently become available and may benefit next revision: -China is building an MHR production facility to support a small fleet of gas-cooled reactors. A search of trade press and international nuclear publications might yield some useful cost data. -X-Energy in the United States is working on MHR development. They may have done some of their own economic analyses; however, these are likely to be proprietary information. Two U.S. corporations, CENTRUS Corporation (Oak Ridge, TN) and Global Nuclear Fuels (Wilmington, NC), are now partnering with X-Energy on TRISO fuel development in both the United States and Japan (CENTRUS 2017; WNN 2019b; WNN 2020b). -BWX Technologies (or BWXT) of Lynchburg, VA is planning a small production line for TRISO fuel for modular and microreactors intended for defense, aerospace, and special industrial applications. Any cost information is likely to be proprietary (WNN 2019a; WNN 2020a; WNN 2020c; WNN 2020e). -Ultra Safe Nuclear Corp plans to use TRISO-coated particles for its fully ceramic encapsulated fuel. This fuel type has possible application as an accident tolerant fuel for water reactors. Their development center will be located in Salt Lake City, UT (Patel 2021). Again any cost information is likely to be proprietary. -HOLOS-GEN has prepared a TRISO-based fuel cartridge design for a portable microreactor for use by the military in remote locations. INL/EXT-21-64514 (September 2021) D1-3-vii Advanced Fuel Cycle Cost Basis

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Section: D1-312 Basic Information From 2009 Afc-cbdmentioning

confidence: 99%

Advanced Fuel Cycle – Cost Basis Report: Module D1-3 Uranium-based Ceramic Particle Fuel Fabrication

Williams,

Hansen,

Hoffman

2021

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“…by the pairs (2,4), (3, I), (7,2) and (5,3), because P is a common nodal point of the elements 2, 3, 5 7 . By assuming continuity of the radiosity at the boundary of elements 2 and 3 there is set R: = R i = R' (the pairs (2,4) and (3,1) are the elements of the set M').…”

Section: Pairs ( I P) If the Integrals Inmentioning

confidence: 99%

Solution of radiative problems using variational based finite element method

Breitbach

Altes²,

Sczimarowsky³

1990

Numerical Meth Engineering

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SUMMARYThe calculation of temperature distributions for systems exchanging radiation heat requires as a first step the determination of the heat fluxes caused by radiation at its surfaces. The functional of the variational principle is the starting point of a numerical solution method.By using finite element procedures a system of linear equations is derived, which supplies an approximation of the radiosity. Having the radiosity, the heat flux at the surfaces, which governs the boundary condition for the temperature distribution in the structure, can be calculated. A method of determining the view-factors using the concept of the finite element method is also given.

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“…The HTGR is an advanced, high efficiency, converter reactor system, which in addition to electrical generation, offers a unique capability to meet industrial requirements for high-temperature process steam and process heat. This paper is not intended to again exalt the merits of the HTGR, since these have been covered previously (1), but rather to briefly outline the currently perceived deployment strategy.…”

Section: Htgr Deploymentmentioning

confidence: 99%

“…Various applications of the HTGR have been studied (2=4), and the next stage of development is to demonstrate full-scale commercial technology. Figure 1 shows the evolution of the HTGR and portrays advancement to the more complex hightemperature systems in an orderly manner as: (1) commercial operating experience is gained with the near-term steam cycle, (2) technical issues are resolved for the higher temperature systems, and (3) the applications and marketplace for the very hightemperature systems are better defined.…”

Section: Htgr Deploymentmentioning

confidence: 99%

The Nuclear Gas Turbine: A Perspective on a Long-Term Advanced Technology HTGR Plant Option

McDonald

Peinado

1982

Volume 3: Coal, Biomass and Alternative Fuels; Combustion and Fuels; Oil and Gas Applications; Cycle Innovations

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Design studies and assessments were carried out in the 1970s on an advanced, direct-cycle high-temperature gas-cooled reactor (HTGR) option. These led to conclusions in 1980 that an extensive development effort was necessary to establish a technically viable gas turbine HTGR (HTGR-GT) plant to satisfy demanding safety and licensing criteria and that further design innovation was necessary to identify plant features for improved economics. The steam cycle HTGR was designated as the lead plant and the HTGR-GT classed as a long-term, advanced technology, second-generation HTGR plant option. With the necessary development, a dry-cooled gas turbine plant with a reactor outlet temperature of approximately 950°C, operating in a combined cycle mode or cogeneration mode, could be realized. This paper reviews the status of the Brayton cycle plant and gives a perspective on the HTGR-GT plant as a follow-on option to the steam Rankine cycle lead plant.

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Gas-Cooled Nuclear Power Reactors

Cited by 24 publications

References 0 publications

Advanced Fuel Cycle – Cost Basis Report: Module D1-3 Uranium-based Ceramic Particle Fuel Fabrication

Advanced Fuel Cycle – Cost Basis Report: Module D1-3 Uranium-based Ceramic Particle Fuel Fabrication

Solution of radiative problems using variational based finite element method

The Nuclear Gas Turbine: A Perspective on a Long-Term Advanced Technology HTGR Plant Option

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