Challenge problem and milestones for : Nuclear Energy Advanced Modeling and Simulation (NEAMS) waste Integrated Performance and Safety Codes (IPSC).

Freeze, Geoffrey A. ; Wang, Yifeng ; Howard, Robert ; McNeish, Jerry A. ; Schultz, Peter Andrew ; Arguello, Jose Guadalupe, Jr.

关键词: AR FACILITIES;    BOROSILICATE GLASS;    NUCLEAR ENERGY;    PERFORMANCE;    POSITIONING;    RADIOACTIVE WASTE STORAGE;    RADIOISOTOPES;    SAFETY;    SIMULATION;    SPECIFICATIONS;    TRANSPORT;    VALIDATION;    VER;   

DOI  :  10.2172/1011222
RP-ID  :  SAND2010-7175
PID  :  OSTI ID: 1011222
Others  :  TRN: US1102165

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

This report describes the specification of a challenge problem and associated challenge milestones for the Waste Integrated Performance and Safety Codes (IPSC) supporting the U.S. Department of Energy (DOE) Office of Nuclear Energy Advanced Modeling and Simulation (NEAMS) Campaign. The NEAMS challenge problems are designed to demonstrate proof of concept and progress towards IPSC goals. The goal of the Waste IPSC is to develop an integrated suite of modeling and simulation capabilities to quantitatively assess the long-term performance of waste forms in the engineered and geologic environments of a radioactive waste storage or disposal system. The Waste IPSC will provide this simulation capability (1) for a range of disposal concepts, waste form types, engineered repository designs, and geologic settings, (2) for a range of time scales and distances, (3) with appropriate consideration of the inherent uncertainties, and (4) in accordance with robust verification, validation, and software quality requirements. To demonstrate proof of concept and progress towards these goals and requirements, a Waste IPSC challenge problem is specified that includes coupled thermal-hydrologic-chemical-mechanical (THCM) processes that describe (1) the degradation of a borosilicate glass waste form and the corresponding mobilization of radionuclides (i.e., the processes that produce the radionuclide source term), (2) the associated near-field physical and chemical environment for waste emplacement within a salt formation, and (3) radionuclide transport in the near field (i.e., through the engineered components - waste form, waste package, and backfill - and the immediately adjacent salt). The initial details of a set of challenge milestones that collectively comprise the full challenge problem are also specified.