ASME Code Efforts Supporting HTGRs

D.K. Morton

关键词: CONSTRUCTION;    ELECTRICITY;    ENGINEERS;    GAS COOLED REACTORS;    NUCLEAR ENERGY;    PROCESS HEAT;    PROLIFERATION Next Generation Nuclear Plant Project;    NGNP;   

DOI  :  10.2172/1031677
RP-ID  :  INL/EXT-10-19518
PID  :  OSTI ID: 1031677
Others  :  TRN: US1200194

美国|英语

来源: SciTech Connect

【 摘 要 】

In 1999, an international collaborative initiative for the development of advanced (Generation IV) reactors was started. The idea behind this effort was to bring nuclear energy closer to the needs of sustainability, to increase proliferation resistance, and to support concepts able to produce energy (both electricity and process heat) at competitive costs. The U.S. Department of Energy has supported this effort by pursuing the development of the Next Generation Nuclear Plant, a high temperature gas-cooled reactor. This support has included research and development of pertinent data, initial regulatory discussions, and engineering support of various codes and standards development. This report discusses the various applicable American Society of Mechanical Engineers (ASME) codes and standards that are being developed to support these high temperature gascooled reactors during construction and operation. ASME is aggressively pursuing these codes and standards to support an international effort to build the next generation of advanced reactors so that all can benefit.