Analysis of Steam-Entry Experiments in the Phase-I GCFR Critical Assembly
- General Atomic Co., San Diego, CA (United States)
The initial three-phase program of critical experiments conducted in behalf of design and safety evaluations for the 300-MW(e) GCFR demonstration plant included extensive studies of steam-entry effects. This report presents results of a General Atomic analysis of the simulated steam ingress experiments in a central 47-liter region of the 3150-liter-core Phase-I GCFR assembly. Investigations of differences in calculated steam worth due to variations in analytical technique are reported, including methods for cross-section generation, adjustments for heterogeneity, neutron-streaming effects, group structure, and the use of various stages of perturbation theory. For each of the densities of steam simulated by CI2 (up to the equivalent of 45 g/liter H2O in the "coolant" channels), the regeneration of cross-section sets for the zone fuel materials with the hydrogen-degraded spectra was found essential for obtaining reasonable agreement of calculated and measured flooding worths. Also, it was necessary to use exact perturbation theory methods, since first-order perturbation was found to be completely inappropriate with the 10- and 28-group structures employed.
- Research Organization:
- General Atomic Co., San Diego, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- EY-76-C-03-0167-023
- OSTI ID:
- 5010459
- Report Number(s):
- GA-A--14798
- Country of Publication:
- United States
- Language:
- English
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