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Title: Monte Carlo calculational design of an NDA instrument for the assay of waste products from high enriched uranium spent fuels

Conference ·
OSTI ID:5625319

The Monte Carlo design of the waste assay region of a dual assay system, to be installed at the Fluorinal and Storage Facility, is described. The instrument will be used by the facility operator to assay high-enriched spent fuel packages and waste solids produced from dissolution of the fuels. The fissile content discharged in the waste is expected to vary between 0 and 400 g of /sup 235/U. Material accountability measurements of the waste must be obtained in the presence of large neutron (0.5 x 10/sup 6/ n/s) and gamma (50,000 R/hr) backgrounds. The assay system employs fast-neutron irradiation of the sample, using a 5 mg /sup 252/Cf source, followed by delayed neutron counting after the source is transferred to storage. Calculations indicate a +-4-g (2 sigma) assay for a waste canister containing 300 g of /sup 235/U is achievable with an end-of-life (1 mg) /sup 252/Cf source and a background rate of 0.5 x 10/sup 6/ n/s.

Research Organization:
Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
DOE Contract Number:
W-7405-ENG-36
OSTI ID:
5625319
Report Number(s):
LA-UR-79-3218; CONF-791117-4; TRN: 80-001895
Resource Relation:
Conference: ANS topical conference, Kiawah Island, SC, USA, 26 Nov 1979
Country of Publication:
United States
Language:
English