Results 41 to 50 of about 2,358 (111)
Advances in HTGR fuel performance models [PDF]
, 1985 Fuel performance models based on empirical evidence are used to predict particle failure and fission product release in the design of high-temperature gas-cooled reactors (HTGRs).
Goodin, D. T. +3 more
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Modular HTGR Safety Basis and Approach [PDF]
, 2011 The Next Generation Nuclear Plant (NGNP) will be a licensed commercial high temperature gas-cooled reactor (HTGR) capable of producing electricity and/or high temperature process heat for industrial markets supporting a range of end-user applications ...
Hicks, Thomas, null Thomas Hicks
core +1 more source
Summary of foreign HTGR programs
, 1980 This report contains pertinent information on the status, objectives, budgets, major projects and facilities, as well as user, industrial and governmental organizations involved in major foreign gas-cooled thermal reactor programs.
core +1 more source
HTGR fuel reprocessing technology
, 1976 The following aspects of HTGR reprocessing technology are discussed: characteristics of HTGR fuels, criteria for a fuel reprocessing flowsheet; selection of a reference reprocessing flowsheet, and waste treatment ...
Brooks, L. H. +2 more
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Htgr Kogenerasi Produksi Hidrogen untuk Konversi Co2 Menjadi Metanol [PDF]
, 2015 HTGR KOGENERASI PRODUKSI HIDROGEN UNTUK KONVERSI CO2 MENJADI METANOL. Telah dilakukan studi HTGR (High Temperature Gas-cooled Reactor) kogenerasi produksi hidrogen untuk konversi CO2 menjadi metanol. Metode yang digunakan adalah studi pustaka.
Salimy, D. H. (Djati), Alimah, S. (Siti)
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Research on Irradiation Production of 238Pu by HTGR and PWR [PDF]
Plutonium-238 (238Pu) is an ideal isotopic heat source commonly used in the production of radioisotope thermoelectric generators (RTGs). It has broad applications in fields such as space exploration and polar meteorological research.
TAN Bo, WEN Yutong, SHE Ding, XIA Bing
core +1 more source
HTGR fuel particle crusher design evaluation [PDF]
, 1978 This report describes an evaluation of the design of the existing engineering-scale fuel particle crushing system for the HTGR reprocessing cold pilot plant at General Atomic Company (GA).
Johanson, N.W.
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, 1980 Progress in the design of an 1170-MW(t) High-Temperature Gas-Cooled Reactor (HTGR) Nuclear Steam Supply (NSS) is described. This NSS can integrate favorably into present petrochemical and primary metal process industries, heavy oil recovery operations ...
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Cesium transport data for HTGR systems [PDF]
, 1979 Cesium transport data on the release of cesium from HTGR fuel elements are reviewed and discussed. The data available through 1976 are treated. Equations, parameters, and associated variances describing the data are presented.
Bell, W. E., Myers, B. F.
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HTGR Fuel performance basis [PDF]
, 1982 The safety characteristics of the high-temperature gas-cooled reactor (HTGR) during normal and accident conditions are determined in part by HTGR fuel performance.
Jensen, D. D. +2 more
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