Preliminary Study Of Transient Safety Analysis Method In Sodium-cooled Fast Reactor

The safety analysis and transient conditions of the accident in Sodium-Cooled Fast Reactor have been always concerned by domestic and international nuclear experts. Multi-dimensionals neutron transport with thermal hydraulics transient coupled principle safety analysis programs are the development trend of reactor safety analysis and evaluation methods, and they are adapted to the structural design of advanced reactor cores which are uncertainty, the neutron flux anisotropy and the designs of future advanced reactor in precision of the core nuclear thermal neutron flux changes over space and time.This article is about the transplantation and preliminary development of the program that encoded in neutron transport theory coupled with thermal hydraulics transient security analysis methods. Thermal fluid part of the program Involved two-dimensional, three-speed field, multiphase flow, the Euler model of multi-component. In the part of neutronics, it adapts the discrete ordinate method in the quasi-static method, which if suit to the design of sodium cooled fast reactor neutron flux uncertainty and the characteristics of a strong anisotropy. Cross section account the Bonderenko theory of resonance self-shielding effect. This article also summarizes sodium-cooled fast reactor system operating conditions and transient accident, and it details of the safety analysis in transient sodium cooled fast reactor accident conditions in a typical unprotected loss of flow accident. Loss of flow accident is one of the typical design basis accidents and it may result in sodium-cooled fast reactor core cooling failure or serious damage. The most typical accident caused by loss of flow is the first event caused the entire plant off the main coolant pump all of outages. Through the process of calculation and analysis power reactor, the reaction of change and the temperature field and velocity field distribution. In which,discover and summarize transient sodium cooled fast reactor safety features and principles. In the end, this article analysis of the uncertainty of the discrete ordinate the main parameters of the program. Discrete ordinate method in the selection of key variables have a critical influence on the results, and inappropriate parameter selection will directly affect the validity and accuracy of the results. The main parameters are given a reasonable selection by analyzing.