Open AccessAnalysis of the peach bottom 2 BWR turbine trip experiment by RELAP 5/3.2 code
Author(s) -
Anis Bousbia-Salah,
F. D’Auria
Publication year - 2002
Publication title -
nuclear technology and radiation protection
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.31
H-Index - 16
eISSN - 1452-8185
pISSN - 1451-3994
DOI - 10.2298/ntrp0202044b
Subject(s) - boiling water reactor , nuclear engineering , neutron transport , transient (computer programming) , computer science , boiling , code (set theory) , turbine , steam turbine , nuclear power plant , nuclear reactor , simulation , environmental science , mechanical engineering , neutron , engineering , physics , nuclear physics , set (abstract data type) , thermodynamics , programming language , operating system
This paper presents the results of the application of the system of the thermalhydraulic code RELAP5/Mod3.2 in predicting the Peach Bottom Boiling Water Reactor Turbine Trip test. This experiment constitutes a challenge to the capabilities of current computational tools in realistically predicting transient scenarios in nuclear power plants. In fact, it involves strong feedback during the transient between thermalhydraulics and neutronics. In this respect, a reference case was run in order to simulate the interactions between the generated steam line pressure wave propagation and the instantaneous core void distribution. An overall comparison shows good agreement between the code calculations and the experimental data. A series of sensitivity analyses were also performed in order to assess the code prediction features, as well as to identify uncertainties related to the adopted thermalhydraulic parameters used for the plant modelisation