Californium-252 assay system for FBR-type fuel pins

Journal Article · Thu Nov 01 04:00:00 EST 1973 · Nucl. Technol., v. 20, no. 2, pp. 124-133

OSTI ID:4403153

Menlove, H O; Forster, R A; Parker, J L; Smith, D B

A hybrid assay system utilizing both active and passive techniques has been built for the measurement of the plutonium fissile content in fast-breeder- reactor-type fuel pins. A moderated /sup 252/Cf source (~600 mu g) is used for the neutron interrogation of the fuel rods, and the fissile content is then determined by counting the high-energy delayed gamma rays resulting from the induced fission reactions. Neutron transport calculations using both S/sub n/ and Monte Carlo techniques were used to design the /sup 252/Cf neutron tailoring assembly to give an intense fast-neutron irradiation, as well as a high fissile/ fertile fission ratio. In addition to the total fissile active assay, pellet-to- pellet uniformity is determined simultaneously by counting the lower energy passive gamma rays from the fuel using the same NaI detectors. The complete assay system, which includes automated fuel-rod handling and data reduction, is being used for in-plant measurements of Fast Flux Test Facility fuel pins. (auth)

• Research Organization: Los Alamos Scientific Lab., NM
• NSA Number: NSA-29-003140
• OSTI ID: 4403153
• Journal Information: Nucl. Technol., v. 20, no. 2, pp. 124-133, Journal Name: Nucl. Technol., v. 20, no. 2, pp. 124-133; ISSN NUTYB
• Country of Publication: Country unknown/Code not available
• Language: English

Related Subjects

*FFTF REACTOR-- FUEL PINS
*FUEL PINS-- CHEMICAL ANALYSIS
*LMFBR TYPE REACTORS-- FUEL PINS
*PLUTONIUM 239-- CHEMICAL ANALYSIS
*SAFEGUARDS-- URANIUM 235
*URANIUM 235-- CHEMICAL ANALYSIS
CALIFORNIUM 252
N52120* --Nuclear Materials & Waste Management-- Accountability & Safeguards--Technical
NEUTRON SOURCES
NUCLEAR MATERIALS MANAGEMENT