Simulator platform for fast reactor operation and safety technology demonstration

Vilim, R. B. ; Park, Y. S. ; Grandy, C. ; Belch, H. ; Dworzanski, P. ; Misterka, J. (Nuclear Engineering Division)

关键词: ANL;    COMPUTER CODES;    DESIGN;    FAST REACTORS;    HUMAN FACTORS;    IN-SERVICE INSPECTION;    MAINTENANCE;    MECHANICAL STRUCTURES;    SAFETY;    SIMULATORS;   

DOI  :  10.2172/1047446
RP-ID  :  ANL-ARC-208
PID  :  OSTI ID: 1047446
Others  :  TRN: US1203988

美国|英语

来源: SciTech Connect

【 摘 要 】

A simulator platform for visualization and demonstration of innovative concepts in fast reactor technology is described. The objective is to make more accessible the workings of fast reactor technology innovations and to do so in a human factors environment that uses state-of-the art visualization technologies. In this work the computer codes in use at Argonne National Laboratory (ANL) for the design of fast reactor systems are being integrated to run on this platform. This includes linking reactor systems codes with mechanical structures codes and using advanced graphics to depict the thermo-hydraulic-structure interactions that give rise to an inherently safe response to upsets. It also includes visualization of mechanical systems operation including advanced concepts that make use of robotics for operations, in-service inspection, and maintenance.