Experimental and theoretical studies of criticality safety by ingress of water in systems with pebble-bed high-temperature gas-cooled reactor fuel
Journal Article
·
· Nucl. Sci. Eng., v. 57, no. 4, pp. 328-332
OSTI ID:4077359
Experiments in a subcritical assembly with pebble-bed high-temperature gas-cooled reactor fuel and hydrogen ranging between 0 and 14.4 vol percent were carried out to study the effects of water ingress in reactivity and to test the accuracy of diffusion-code calculations for small subcritical systems. Special emphasis is given to an adequate description of the influence of the water ingress on the diffusion properties of the pebble-bed system. The agreement between experimental and theoretical results is in all cases better than +-0.01 in k/sub eff/.(auth)
- Research Organization:
- Kernforschungsanlage, Juelich, Ger.
- NSA Number:
- NSA-33-016437
- OSTI ID:
- 4077359
- Journal Information:
- Nucl. Sci. Eng., v. 57, no. 4, pp. 328-332, Other Information: Orig. Receipt Date: 30-JUN-76
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
N77900* -Reactors-Reactor Safety & Environmental Aspects
N77300 -Reactors-Power Reactors
Non-breeding
Graphite Moderated
N52300 -Nuclear Materials & Waste Management-Handling Equipment & Procedures
220900* -Nuclear Reactor Technology-Reactor Safety
*CRITICALITY
*FUEL ASSEMBLIES- CRITICALITY
*HTGR TYPE REACTORS- FUEL ASSEMBLIES
*PEBBLE BED REACTORS- FUEL ASSEMBLIES
HYDROGEN
RADIATION ACCIDENTS
REACTOR ACCIDENTS
REACTOR SAFETY
STORAGE
TRANSPORT
WATER
N77300 -Reactors-Power Reactors
Non-breeding
Graphite Moderated
N52300 -Nuclear Materials & Waste Management-Handling Equipment & Procedures
220900* -Nuclear Reactor Technology-Reactor Safety
*CRITICALITY
*FUEL ASSEMBLIES- CRITICALITY
*HTGR TYPE REACTORS- FUEL ASSEMBLIES
*PEBBLE BED REACTORS- FUEL ASSEMBLIES
HYDROGEN
RADIATION ACCIDENTS
REACTOR ACCIDENTS
REACTOR SAFETY
STORAGE
TRANSPORT
WATER