2007 International RERTR Meeting

Abstracts and Available Papers Presented at the Meeting

MNSR Transient Analyses and Thermal-Hydraulic Safety Margins for HEU and LEU Cores Using PARET

Arne P. Olson¹, S.A. Jonah²,

¹ RERTR Program
Argonne National Laboratory, Argonne, IL USA 60439

² Centre for Energy Research and Training
Ahmadu Bello University, Zaria
P.M.B. 1014, Nigeria

ABSTRACT

Thermal-hydraulic performance characteristics of Miniature Neutron Source Reactors under long-term steady-state and transient conditions are investigated. Safety margins and limiting conditions attained during these events are determined. Modeling extensions are presented that enable the PARET/ANL code to realistically track primary loop heatup, heat exchange to the pool, and heat loss from the pool to air over the pool. Comparisons are made of temperature predictions for HEU and LEU fueled cores under transient conditions. Results are obtained using three different natural convection heat transfer correlations: the original (PARET/ANL version 5), Churchill-Chu, and an experiment-based correlation from the China Institute of Atomic Energy (CIAE). The MNSR, either fueled by HEU or by LEU, satisfies the design limits for long-term transient operation.

 

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