Uncertainties of the ENDF/B-V /sup 238/U unresolved resonance parameters in the range 4 keV < E < 45. 18 keV (MAT = 1398, MF = 2, MT = 251)
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:5995198
It is a common practice in ENDF/B to represent neutron cross sections in the unresolved resonance region by specifying the average values and distribution laws of resonance parameters. This formalism allows the calculation of resonance self-shielding and of the variation of resonance self-shielding with temperature, two important reactor parameters. For many applications it is necessary to estimate the uncertainties in these model average resonance parameters. A possible approach to derive such uncertainties is described, using as an example the ENDF/B-V representation of /sup 238/U in the range from 4 to 45 keV.
- Research Organization:
- Oak Ridge National Lab., TN (USA). Engineering Physics and Mathematics Div.
- OSTI ID:
- 5995198
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 101:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Evaluation of the unresolved resonance range of sup 238 U + n. Part 2; Differential data tests
Test of the ENDF/B (Evaluated Nuclear Data File) unresolved resonance formalism for sup 235 U
Evaluation of the unresolved resonance range of sup 238 U
Journal Article
·
Sat Aug 01 00:00:00 EDT 1992
· Nuclear Science and Engineering; (United States)
·
OSTI ID:7274396
Test of the ENDF/B (Evaluated Nuclear Data File) unresolved resonance formalism for sup 235 U
Conference
·
Tue Oct 31 23:00:00 EST 1989
· Transactions of the American Nuclear Society; (United States)
·
OSTI ID:5419256
Evaluation of the unresolved resonance range of sup 238 U
Journal Article
·
Sun Oct 01 00:00:00 EDT 1989
· Nuclear Science and Engineering; (USA)
·
OSTI ID:6964238
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
653003 -- Nuclear Theory-- Nuclear Reactions & Scattering
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYONS
CALCULATION METHODS
CROSS SECTIONS
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
NEUTRONS
NUCLEONS
PARAMETRIC ANALYSIS
REACTORS
SHIELDING
TARGETS
THERMAL NEUTRONS
UNCERTAINTY PRINCIPLE
URANIUM 238 TARGET
220100* -- Nuclear Reactor Technology-- Theory & Calculation
653003 -- Nuclear Theory-- Nuclear Reactions & Scattering
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYONS
CALCULATION METHODS
CROSS SECTIONS
ELEMENTARY PARTICLES
ENRICHED URANIUM REACTORS
FERMIONS
HADRONS
NEUTRONS
NUCLEONS
PARAMETRIC ANALYSIS
REACTORS
SHIELDING
TARGETS
THERMAL NEUTRONS
UNCERTAINTY PRINCIPLE
URANIUM 238 TARGET