NULIF: neutron spectrum generator, few-group constant calculator, and fuel depletion code
Description
The NULIF code generates a microgroup neutron spectrum and calculates spectrum-weighted few-group parameters for use in a spatial diffusion code. A wide variety of fuel cells, non-fuel cells, and fuel lattices, typical of PWR (or BWR) lattices, are treated. A fuel depletion routine and change card capability allow a broad range of problems to be studied. Coefficient variation with fuel burnup, fuel temperature change, moderator temperature change, soluble boron concentration change, burnable poison variation, and control rod insertion are readily obtained. Heterogeneous effects, including resonance shielding and thermal flux depressions, are treated. Coefficients are obtained for one thermal group and up to three epithermal groups. A special output routine writes the few-group coefficient data in specified format on an output tape for automated fitting in the PDQ07-HARMONY system of spatial diffusion-depletion codes
Availability note (English)
MF available from INIS under the Report Number; Babcock and Wilcox, Lynchburg, VA.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Additional titles
- Augmented title (English)
- PWR and BWR
Publishing Information
- Imprint Pagination
- 124 p.
- Report number
- BAW--10115A
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8338250
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; COMPUTER CODES; FUEL ASSEMBLIES; N CODES; NEUTRON SPECTRA; PWR TYPE REACTORS; REACTOR CORES; REACTOR KINETICS
- Descriptors DEC
- KINETICS; REACTOR COMPONENTS; REACTORS; SPECTRA; WATER COOLED REACTORS; WATER MODERATED REACTORS