Advanced Test Reactor Core Modeling Update Project Annual Report for Fiscal Year 2010

Rahmat Aryaeinejad ; Douglas S. Crawford ; Mark D. DeHart ; George W. Griffith ; D. Scott Lucas ; Joseph W. Nielsen ; David W. Nigg ; James R. Parry ; Jorge Navarro

关键词: ACCURACY;    EFFICIENCY;    FUEL MANAGEMENT;    MANAGEMENT;    NUCLEAR ENGINEERING;    REACTOR PHYSICS;    SAFETY;    SIMULATION;    TEST REACTORS Advanced Test Reactor;    ATR Core Fuel Management;    Legacy;   

DOI  :  10.2172/1009157
RP-ID  :  INL/EXT-10-19940
PID  :  OSTI ID: 1009157
Others  :  TRN: US1101740

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来源: SciTech Connect

【 摘 要 】

Legacy computational reactor physics software tools and protocols currently used for support of Advanced Test Reactor (ATR) core fuel management and safety assurance and, to some extent, experiment management are obsolete, inconsistent with the state of modern nuclear engineering practice, and are becoming increasingly difficult to properly verify and validate (V&V). Furthermore, the legacy staff knowledge required for application of these tools and protocols from the 1960s and 1970s is rapidly being lost due to staff turnover and retirements. In 2009 the Idaho National Laboratory (INL) initiated a focused effort to address this situation through the introduction of modern high-fidelity computational software and protocols, with appropriate V&V, within the next 3-4 years via the ATR Core Modeling and Simulation and V&V Update (or ???Core Modeling Update???) Project. This aggressive computational and experimental campaign will have a broad strategic impact on the operation of the ATR, both in terms of improved computational efficiency and accuracy for support of ongoing DOE programs as well as in terms of national and international recognition of the ATR National Scientific User Facility (NSUF).