The gas-cooled fast breeder reactor critical experiments program
| Autor: | R.J. Cerbone, E.M. Bohn, L.G. LeSage, S.K. Bhattacharyya, A.L. Hess, R.A. Moore, R.B. Pond |
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| Rok vydání: | 1977 |
| Předmět: |
Physics
Nuclear and High Energy Physics Waste management Mechanical Engineering Nuclear engineering Boiler (power generation) chemistry.chemical_element Nuclear data Coolant Reaction rate Nuclear Energy and Engineering chemistry Cabin pressurization Breeder reactor General Materials Science Neutron Safety Risk Reliability and Quality Waste Management and Disposal Helium |
| Zdroj: | Nuclear Engineering and Design. 40:27-41 |
| ISSN: | 0029-5493 |
| DOI: | 10.1016/0029-5493(77)90149-2 |
| Popis: | This paper presents results of measurements and calculations of physics parameters in the first gas-cooled fast breeder reactor (GCFR) critical assemblies in the US, a program of experiments conducted on the ZPR-9 facility at Argonne National Laboratory. Through a progressive three-phase series of assemblies, the major features unique to GCFR physics due to the gaseous coolant, and the resulting hard neutron spectrum and greater leakage, were investigated. Phases I and II were simple-geometry, uniform-core assemblies providing tests of nuclear data and GCFR design methods for fast reactors with large void fractions. The Phase III core simulates a GCFR design with three enrichment zones. This report primarily concerns the results obtained in Phase II. In addition to the usual central indices, reaction rate mappings, etc. these initial studies have provided the first experimental data on reactivity coefficients relevant to GCFR safety, such as worths of fuel, control, and cladding materials, Doppler effect, and coolant (helium) depressurization worth. Effects of steam ingress into coolant channels (due to a hypothesized steam generator leak) were simulated using polyethylene. The physics information obtained is providing a valuable base for verification of GCFR design and safety analyses. |
| Databáze: | OpenAIRE |
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