Fast Breeder Blanket Facility FBBF. Annual report, January 1, 1981-December 31, 1981
- ed.
This annual report contains a summmary of fission rate, spectra, and gamma-ray heating rate measurements made in the first blanket of the Purdue Fast Breeder Blanket Facility. The first blanket consisted of aluminum clad, natural UO/sub 2/ fuel rods with a secondary cladding of stainless steel or aluminum. The blanket was arranged in two concentric regions around the neutron source and converter regions. A neutron diffusion code, 2DB, and a Monte Carlo code, VIM, both using homogeneous cross section groups have been used to calculate the reaction rates. Calculated to experimental values for a number of important reactions are presented. A modified method of applying Bondarenko self-shielding factors to correct for the self shielding of resonance energy neutrons in aluminum, stainless steel and UO/sub 2/ has improved the agreement between the calculations and experiment, but does not account for all of the differences.
- Research Organization:
- Purdue Univ., Lafayette, IN (USA). School of Nuclear Engineering
- Sponsoring Organization:
- USDOE
- DOE Contract Number:
- AC02-76ET37237
- OSTI ID:
- 6948919
- Report Number(s):
- DOE/ET/37237-16; COO-2826-16; PNE-82-153; ON: DE82021044
- Country of Publication:
- United States
- Language:
- English
Similar Records
Fast Breeder Blanket Facility (Interim Report, January 1981)
Fast Breeder Blanket Facility. Quarterly progress report, January 1, 1979-March 31, 1979
Related Subjects
210500* -- Power Reactors
Breeding
BREEDER REACTORS
BREEDING BLANKETS
COMPARATIVE EVALUATIONS
COMPUTER CALCULATIONS
EPITHERMAL REACTORS
FAST REACTORS
FBR TYPE REACTORS
HEATING
KINETICS
MOCKUP
NEUTRON SPECTRA
RADIATION HEATING
REACTION KINETICS
REACTOR COMPONENTS
REACTOR KINETICS
REACTORS
SPECTRA
STRUCTURAL MODELS
TEST FACILITIES