Open AccessBurn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1
Author(s) -
Atta Muhammad,
Masood Iqbal,
Tayyab Mahmood
Publication year - 2011
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/ntrp1101045m
Subject(s) - burnup , nuclear engineering , thermal hydraulics , research reactor , steady state (chemistry) , xenon , boiling water reactor , coolant , materials science , nuclear reactor core , core (optical fiber) , environmental science , thermodynamics , nuclear physics , chemistry , physics , heat transfer , engineering , neutron , composite material
The burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1, reference operating core, has been carried out utilizing standard computer codes WIMS/D4, CITATION, and RELAP5/MOD3.4. Reactor codes WIMS/D4 and CITATION have been used for the calculations of neutronic parameters including peaking factors and power profiles at different burn-up considering a xenon free core and also the equilibrium xenon values. RELAP5/MOD3.4 code was utilized for the determination of peak fuel centerline, clad and coolant temperatures to ensure the safety of the reactor throughout the cycle. The calculations reveal that the reactor is safe and no nucleate boiling will commence at any part of the core throughout the cycle and that the safety margin increases with burnup as peaking factors decrease