Validation of COOLOD-N2 Code Through Benchmark Calculations of IEA-R1 Reactor

N. H. Badrun, M. H. Altaf, M. J. H. Khan

Abstract


IEA-R1 reactor core has been modeled in COOLOD-N2 code with the aim to validate and verify the code against the experiment data provided by International Atomic Energy Agency (IAEA) through coordinated research project (CRP). Fuel cladding temperatures at different locations of an instrumental fuel assembly (IFA) at different operating powers have been calculated under steady state condition by using the COOLOD-N2 code. The calculated temperatures are then verified against the temperatures recorded by thermo couples placed for those locations of IFA in 243 configuration of IEA-R1 reactor. Reasonable agreement has been found between the calculation and experiment for fuel clad temperature which in turn implies the validity of COOLOD-N2 code in the calculation of core thermal hydraulic parameters of research reactors under steady state condition.

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References


Masanoroi Kaminaga, COOLOD-N2: A Computer Code for the

Analyses of Steady State Thermal Hydraulic in Research Reactors,

Japan Atomic Energy Research Institute, Japan (1994).

Pedro E. Umbehaun, Reactor and Benchmark Specifications of IEAR1 Reactor, A Document Delivered Through CRP Project of IAEA

(2012)


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