MNSR transient analyses and thermal-hydraulic safety margins for HEU and LEU cores using PARET
- RERTR Program, Argonne National Laboratory, Argonne, IL 60439 (United States)
- Centre for Energy Research and Training, Ahmadu Bello University, Zaria, P.M.B. 1014 (Nigeria)
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. (author)
- Research Organization:
- Argonne National Laboratory, Nuclear Engineering Division, RERTR Department, Argonne, IL (United States); Czech Technical University, Prague (Czech Republic)
- OSTI ID:
- 21113514
- Report Number(s):
- INIS-US-08N0001; TRN: US08N0036121052
- Resource Relation:
- Conference: RERTR-2007: 29. international meeting on reduced enrichment for research and test reactors, Prague (Czech Republic), 23-27 Sep 2007; Other Information: Country of input: International Atomic Energy Agency (IAEA); 11 refs, 9 figs; Related Information: In: 2007 international meeting on Reduced Enrichment for Research and Test Reactors (RERTR). Abstracts and available papers presented at the meeting, vp.
- Country of Publication:
- United States
- Language:
- English
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