Next Generation Nuclear Plant GAP Analysis Report

Ball, Sydney J¹  Burchell, Timothy D¹  Corwin, William R¹  Fisher, Stephen Eugene¹  Forsberg, Charles W.²  Morris, Robert Noel¹  Moses, David Lewis¹ 

[1] ORNL;Massachusetts Institute of Technology (MIT)

关键词: ACCIDENTS;    DESIGN;    FISSION PRODUCTS;    GRAPHITE;    HYDROGEN;    PROCESS HEAT;    PRODUCTION;    RECOMMENDATIONS;    RISK ASSESSMENT;    SAFETY;    TRANSPORT;   

DOI  :  10.2172/946475
RP-ID  :  ORNL/TM-2007/228
PID  :  OSTI ID: 946475
Others  :  Other: 401001060
Others  :  TRN: US200903%%961

学科分类：再生能源与代替技术

美国|英语

来源: SciTech Connect

【 摘 要 】

As a follow-up to the phenomena identification and ranking table (PIRT) studies conducted recently by NRC on next generation nuclear plant (NGNP) safety, a study was conducted to identify the significant 'gaps' between what is needed and what is already available to adequately assess NGNP safety characteristics. The PIRT studies focused on identifying important phenomena affecting NGNP plant behavior, while the gap study gives more attention to off-normal behavior, uncertainties, and event probabilities under both normal operation and postulated accident conditions. Hence, this process also involved incorporating more detailed evaluations of accident sequences and risk assessments. This study considers thermal-fluid and neutronic behavior under both normal and postulated accident conditions, fission product transport (FPT), high-temperature metals, and graphite behavior and their effects on safety. In addition, safety issues related to coupling process heat (hydrogen production) systems to the reactor are addressed, given the limited design information currently available. Recommendations for further study, including analytical methods development and experimental needs, are presented as appropriate in each of these areas.