Nuclear data for /sup 235/U, /sup 238/U, and /sup 239/Pu in the unresolved resonance region

Journal Article · Mon Jun 01 04:00:00 EDT 1987 · Nucl. Sci. Eng.; (United States)

OSTI ID:6061520

Vankov, A A; Ukraintsev, V F; Yaneva, N; Toshkov, S; Mateeva, A

Transmission and fission self-indication were measured for the isotopes /sup 235/U, /sup 238/U, and /sup 239/Pu in the unresolved resonance region for a wide range of material thicknesses. The fission cross section of /sup 235/U serves as standard. The other isotopes are the basic fuel components in plutonium fast breeder reactors. The experimental results obtained were analyzed together with average cross-section data using the multilevel R-matrix formalism. The objective of the consistent analysis was to estimate sets of mean resonance parameters. For this purpose, a new multilevel ladder technique was developed (Monte Carlo method) that enabled calculation of all the functionals of interest including their sensitivity coefficients related to the mean resonance parameters. Hence, the perturbation approach and the correlated random sampling technique were employed.

• Research Organization: Institute of Physics and Power Engineering, SCAE, Obninsk
• OSTI ID: 6061520
• Journal Information: Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 96:2; ISSN NSENA
• Country of Publication: United States
• Language: English

Related Subjects

652020* -- Nuclear Properties & Reactions
A=220 & above
Experimental
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BREEDER REACTORS
CROSS SECTIONS
DIMENSIONS
EPITHERMAL REACTORS
FAST FISSION
FAST REACTORS
FBR TYPE REACTORS
FISSION
HADRON REACTIONS
MATRICES
MONTE CARLO METHOD
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEON REACTIONS
PERTURBATION THEORY
PLUTONIUM 239 TARGET
R MATRIX
REACTORS
RESONANCE
SAMPLING
SENSITIVITY ANALYSIS
TARGETS
THICKNESS
TOTAL CROSS SECTIONS
URANIUM 235 TARGET
URANIUM 238 TARGET