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RISUncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: One of the key elements in probabilistic risk assessment is the identification and characterization of uncertainties. This paper suggests a procedure to identify influencing factors for uncertainty in source term evaluation, ...
HTTR Demonstration Program for Nuclear Cogeneration of Hydrogen and Electricity
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The Japan Atomic Energy Agency (JAEA) initiated a hightemperature engineering test reactor (HTTR) demonstration program in accordance with recommendations of a task force established by the Ministry of Education, Culture, ...
Nuclear Heat Supply Fluctuation Tests by Non-Nuclear Heating With HTTR
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The nuclear heat utilization systems connected to high-temperature gas-cooled reactors (HTGRs) will be designed on the basis of non-nuclear-grade standards in terms of easier entry for the chemical plant companies and the ...