Code Assessment and Applications Assessment of the RELAP4/M0D6 Thermal-Hydraulic Transient Code;Volume I, Assessment Analysis

摘要

The RELAP4/M0D6 computer code was recently released to the public by the Nuclear Regulatory Commission for use in reactor transient thermal-hydraulic analysis. The code has a unique new capability for calculation of both the blowdown and reflood portions of a postulated pressurized water reactor loss-of-coolant accident. Assessment of this code after its release represents the quality-evaluation phase of the code development program. A principal assessment objective is to provide tested and evaluated codes usable in the analysis of hypothesized LWR (light water reactor) accidents. This objective has been met through comparison and evaluation of code calculations with results of thermal-hydraulic experiments.