The ENDF/B-V and ENDF/B-VI reactivity differences for PWR pin cells as a function of enrichment
Journal Article
·
· Transactions of the American Nuclear Society
OSTI ID:186703
- Los Alamos National Lab., NM (United States)
A recent study has concluded that primarily because of changes to the cross sections for uranium 235 and uranium 238, Rev. 2 of the ENDF/B-VI cross section library predicts higher reactivity than does ENDF/B-V for highly enriched uranium fuel in thermal reactors than it predicts lower reactivity for natural or slightly enriched uranium fuel.
- OSTI ID:
- 186703
- Report Number(s):
- CONF-950601--
- Journal Information:
- Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 72; ISSN 0003-018X; ISSN TANSAO
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparisons of ENDF/B-V and ENDF/B-VI results for a variety of thermal-reactor lattices
Comparisons of ENDF/B-V and ENDF/B-VI results for a variety of reactor lattices
ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP
Conference
·
Sat Dec 30 23:00:00 EST 1995
·
OSTI ID:459219
Comparisons of ENDF/B-V and ENDF/B-VI results for a variety of reactor lattices
Conference
·
Thu Mar 31 23:00:00 EST 1994
·
OSTI ID:10186528
ENDF/B-V and ENDF/B-VI results for UO-2 lattice benchmark problems using MCNP
Conference
·
Sat Aug 01 00:00:00 EDT 1998
·
OSTI ID:674737