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Franklin, D.; Marston, T.
Electric Power Research Inst., Palo Alto, CA (USA). Systems and Materials Dept1983
Electric Power Research Inst., Palo Alto, CA (USA). Systems and Materials Dept1983
AbstractAbstract
[en] The concern of neutron embrittlement of reactor pressure vessels can be alleviated by obtaining better dosimetry data and refining estimates of vessel-material embrittlement, by reducing the flux at the vessel wall through alternate fuel-management schemes, or by annealing. This report reviews methods of reducing the fast-neutron flux at the vessel wall by altering fuel-management schemes. The report also includes assessment of the benefits in terms of reactor-vessel integrity from such flux-reduction schemes
Original Title
PWR
Primary Subject
Secondary Subject
Source
May 1983; 28 p; Available from NTIS, PC A03/MF A01 as DE83902227
Record Type
Report
Report Number
Country of publication
ALLOYS, BARYONS, CARBON ADDITIONS, CONTAINERS, ELEMENTARY PARTICLES, FERMIONS, HADRONS, IRON ALLOYS, IRON BASE ALLOYS, MANAGEMENT, MATERIALS, NEUTRONS, NUCLEAR MATERIALS MANAGEMENT, NUCLEONS, RADIATION EFFECTS, RADIATION FLUX, REACTORS, TRANSITION ELEMENT ALLOYS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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