Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors

Journal Article · Thu Mar 01 00:00:00 EST 2012 · Journal of ASTM International

DOI:https://doi.org/10.1520/JAI103959· OSTI ID:1040664

Greenwood, Lawrence R; Wittman, Richard S; Pierson, Bruce D; Metz, Lori A; Payne, Rosara F; Finn, Erin C; Friese, Judah I

A boron carbide capsule has been designed and used for spectral-tailoring experiments at the TRIGA reactor at Washington State University. Irradiations were conducted in pulsed mode and in continuous operation for up to 4 hours. A cadmium cover was used to reduce thermal heating. The neutron spectrum calculated with MCNP was found to be in good agreement with reactor dosimetry measurements using the STAY'SL computer code. The neutron spectrum resembles that of a fast reactor. Design of a capsule using boron carbide enriched in {sup 10}B shows that it is possible to produce a neutron spectrum similar to {sup 235}U fission.

• Research Organization: Pacific Northwest National Lab. (PNNL), Richland, WA (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC05-76RL01830
• OSTI ID: 1040664
• Report Number(s): PNNL-SA-79709; TRN: US1202504
• Journal Information: Journal of ASTM International, Vol. 9, Issue 3; ISSN 1546-962X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
BORON CARBIDES
CADMIUM
COMPUTER CODES
DESIGN
DOSIMETRY
FAST REACTORS
FISSION
HEATING
NEUTRONS
TESTING
reactor dosimetry
boron carbide