Published 1977 | Version v1
Report Restricted

Fast reactor fission yield measurement program at the Idaho National Engineering Laboratory

  • 1. Allied Chemical Corp., Idaho Falls, ID

Description

The INEL fission yield measurement program and the current status of the results are reviewed. Fast reactor fission yields for 233U, 235U, 238U, 239Pu, 241Pu, and 237Np obtained for samples irradiated in Row-8 of EBR-II have been reported. The neutron spectrum associated with the reported yields has been reported. Measurement of fast reactor fission yields for 240Pu, 242Pu, and 241Am is in progress. To supplement these data, and to provide additional correlation points relative to the effect of neutron energy on fission yields, a series of samples previously irradiated in the axial blanket and Row-2 to 4 of EBR-II has been obtained for analysis. Future efforts relative to recommending and prooftesting methods for the analysis of burnup for FBR fuels are discussed

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Additional details

Publishing Information

Imprint Title
Dosimetry methods for fuels, cladding, and structural materials
Journal Page Range
p. 1267-1278.
Report number
NUREG-CP--0004(Vol.3)

Conference

Title
dosimetry methods for fuels, cladding and structural materials.
Acronym
2. ASTM-EURATOM symposium on reactor dosimetry
Dates
2 - 7 Oct 1977.
Place
Palo Alto, CA, USA.