Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1

Burn-up dependent steady-state thermal hydraulic analysis of Pakistan research reactor-1

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...

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Bibliographic Details
Main Authors: Muhammad Atta, Iqbal Masood, Mahmood Tayyab
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2011-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
research reactor
fuel burn-up dependent cross-sections
nuclear peaking factors
power profile
thermal hydraulics
WIMSD/4
CITATION
RELAP5/MOD3.4
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2011/1451-39941101045M.pdf

Internet

http://www.doiserbia.nb.rs/img/doi/1451-3994/2011/1451-39941101045M.pdf

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