MCNP analysis of PNL split-table critical experiments containing mixed-oxide fuels
- Univ. of Texas, Austin, TX (United States)
Pacific Northwest Laboratory (PNL) Split-Table Critical experiments containing mixed-oxide (MOX) fuels for various core configurations are studied using MCNP4A with the ENDF/B-VI continuous-energy library. These experiments were performed to provide necessary technical information and experimental criticality data that would serve as benchmark data in support of the liquid-metal fast breeder reactor program. Because of the current interest in the utilization of weapons-grade plutonium in the form of MOX fuel in light water reactors, such experimental data are extremely important for checking the performance of the modem computational tools. The {sup 239}Pu content in plutonium of the PNL MOX fuels is {approximately}91 wt%, which is very close to that of the weapons-grade {sup 239}Pu. The MOX fuels used in these critical experiments consist of 30.0, 14.62, and 7.89 wt% Pu and N{sub H}/(N{sub Pu} + Nu) moderation ratios (MRs) of 47.4, 30.6, and 51.8, respectively.
- OSTI ID:
- 552478
- Report Number(s):
- CONF-971125-; ISSN 0003-018X; TRN: 98:001687
- Journal Information:
- Transactions of the American Nuclear Society, Vol. 77; Conference: 1997 American Nuclear Society (ANS) winter meeting, Albuquerque, NM (United States), 16-20 Nov 1997; Other Information: PBD: 1997
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of energy spectrum with and without S({alpha},{beta}) treatment for PNL MOX fuel split-table critical experiments
Comparison of ENDF/B-VI and preliminary ENDF/B-VII results for the MCNP criticality validation suite