Boron Injection Transient Analysis in a PWR NPP with RELAP5/PARCS v2.7 Coupled Code
The uncontrolled boron dilution transient belongs to the design-based reactivity initiated accidents (RIA) category of accidents in PWRs. For the purpose of simulating this kind of transients, a coupled thermalhydraulic-neutronic model has been developed. In order to test the model, this work analyzes a boron injection transient in a typical PWR Nuclear Power Plant. The thermalhydraulic model includes all the primary loop components of a PWR, the core fuel channels modeled with PIPE components, pumps, steam generators, pressurizer, etc. The neutronic representation of the reactor has been made in a one-to-one basis fuel channel model for the whole core. The transient has been simulated using the thermalhydraulic-neutronic coupled codes RELAP5-MOD3.3/ PARCS v2.7.
Boron transients coupled codes RELAP5 PARCS
A. Abarca T. Barrachina R. Miró G. Verdú C. Pereira
Institute for Industrial, Radiophysical and Environmental Safety (ISIRYM) Universitat Politècnica de Departamento de Engenharia Nuclear Universidade Federal de Minas GeraisAv. Antonio Carlos 6627, 3127
国际会议
上海
英文
2209-2217
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）