Results 61 to 70 of about 2,358 (111)
HTGR generic technology program. Semiannual report ending March 31, 1980
, 1980 This document reports the technical accomplishments on the HTGR Generic Technology Program at General Atomic during the first half of FY-80. It covers a period when the design direction of the National HTGR Program is in the process of an overall review.
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Application target image of a small modular fluoride salt-cooled high temperature reactor based on the analysis of energy demand and environmental conditions in western China. [PDF]
Heliyon, 2022 Guo Y, Dai Y, Zhang J, Jiang D, Fu Y.
europepmc +1 more source
High-temperature process heat applications with an HTGR [PDF]
, 1980 An 842-MW(t) HTGR-process heat (HTGR-PH) design and several synfuels and energy transport processes to which it could be coupled are described. As in other HTGR designs, the HTGR-PH has its entire primary coolant system contained in a prestressed ...
Vrable, D.L., Quade, R.N.
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Reprocessing yields and material throughput: HTGR recycle demonstration facility
, 1977 Recovery and reuse of residual U-235 and bred U-233 from the HTGR thorium-uranium fuel cycle will contribute significantly to HTGR fuel cycle economics and to uranium resource conservation.
Holder, N., Abraham, L.
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Core seismic methods verification report. [HTGR]
, 1979 Information on HTGR reactor core seismic requirements is presented concerning element properties and code parameters; correlation and verification of the codes; sensitivity studies; and application to ...
Rakowski, J. E. +6 more
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Strata temperatures and geothermal resource evaluation in the Dongpu Depression, Bohai Bay Basin, North China. [PDF]
Sci Rep, 2023 Qiao Y +5 more
europepmc +1 more source
HTGR structural-materials efforts in the US
, 1982 The status of ongoing structural materials programs being conducted in the US to support development and deployment of the high-temperature gas-cooled reactor (HTGR) is described.
Rittenhouse, P.L., Roberts, D.I.
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, 1976 This publication presents results of work performed under the National HTGR Fuel Recycle Program Thorium Utilization Program. The work reported includes the development of unit processes and equipment for reprocessing of HTGR fuel and the design and ...
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Irradiation behavior of pyrolytic silicon carbide. [HTGR] [PDF]
, 1983 Fuel particles for the High-Temperature Gas-Cooled Reactor (HTGR) contain a layer of pyrolytic silicon carbide to act as a miniature pressure vessel and primary fission-product barrier.
Lauf, R.J.
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, 1976 The work reported includes the development of unit processes and equipment for reprocessing of High-Temperature Gas-Cooled Reactor (HTGR) fuel and the design and development of an integrated line to demonstrate the head end of HTGR reprocessing using ...
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