Coupled High Fidelity Thermal Hydraulics and Neutronics for Reactor Safety Simulations. International Conference on Reactor Physics, Nuclear Power: A Sustainable Resource (Preprint).

Mousseau, V. A. ; Zhang, H. ; Zhao, H.

Technical Information Center Oak Ridge Tennessee

关键词: Reactor safety;    Reactor physics;    Accuracy;    Coolants;    Loss of flow;   

RP-ID  :  DE2008940060

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

This work is a continuation of previous work on the importance of accuracy in the simulation of nuclear reactor safety transients. This work is qualitative in nature and future work will be more quantitative. The focus of this work will be on a simplified single phase nuclear reactor primary. The transient of interest investigates the importance of accuracy related to passive (inherent) safety systems. The transient run here will be an Unprotected Loss of Flow (ULOF) transient. Here the coolant pump is turned off and the unSCRAMed reactor transitions from forced to free convection (Natural circulation). Results will be presented that show the difference that the first order in time truncation physics makes on the transient. The purpose of this document is to illuminate a possible problem in traditional reactor simulation approaches. Detailed studies need to be done on each simulation code for each transient analyzed to determine if the first order truncation physics plays an important role.