Skip to main content
OSTI.GOVU.S. Department of Energy Office of Scientific and Technical Information
U.S. Department of Energy
Office of Scientific and Technical Information
 

Test of the ENDF/B (Evaluated Nuclear Data File) unresolved resonance formalism for sup 235 U

Conference · · Transactions of the American Nuclear Society; (United States)
OSTI ID:5419256
; ; ;  [1]
  1. Oak Ridge National Laboratory, TN (USA)
+ Show Author Affiliations
It is common practice in ENDF/B (Evaluated Nuclear Data File) 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 its variation with temperature. The purpose of this paper is to present a test of the validity of the formalism by comparing self-shielding factors computed with the ENDF/B unresolved formalism with values computed with the resolved resonance parameters recently evaluated for the neutron cross sections of {sup 235}U.
OSTI ID:
5419256
Report Number(s):
CONF-891103--
Conference Information:
Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 60
Country of Publication:
United States
Language:
English

Similar Records

On the ENDF/B unresolved resonance region formalism representation for sup 239 Pu
Conference · Fri Jun 01 00:00:00 EDT 1990 · Transactions of the American Nuclear Society; (USA) · OSTI ID:6126832
Practical formalisms for nuclear data representation in evaluated nuclear data files in the unresolved resonance energy region
Journal Article · Tue Feb 28 23:00:00 EST 1978 · Nucl. Sci. Eng.; (United States) · OSTI ID:5134143
On the ENDF/B unresolved resonance region formalism representation for sup 239 Pu
Conference · Sun Dec 31 23:00:00 EST 1989 · OSTI ID:6989445

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100* -- Nuclear Reactor Technology-- Theory & Calculation
651000 -- Nuclear Physics
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
99 GENERAL AND MISCELLANEOUS
990300 -- Information Handling
ACTINIDE ISO
ACTINIDE NUCLEI
ACTINIDES
ALPHA DECAY RADIOISOTOPES
BARYON REACTIONS
BREIT-WIGNER FORMULA
CAPTURE
CROSS SECTIONS
DATA
DOCUMENTATION
DOPPLER EFFECT
ELEMENTS
ENRICHED URANIUM
EVALUATED DATA
EVEN-ODD NUCLEI
FISSION
GROUP THEORY
HADRON REACTIONS
HEAVY NUCLEI
INFORMATION
INTEGRALS
INTERNAL CONVERSION RADIOISOTOPES
ISOMERIC TRANSITION ISOTOPES
ISOTOPE ENRICHED MATERIALS
ISOTOPES
MATERIALS
MATHEMATICS
METALS
MINUTES LIVING RADIOISOTOPES
NATIONAL ORGANIZATIONS
NEUTRON REACTIONS
NUCLEAR DATA COLLECTIONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUMERICAL DATA
ORNL
PHYSICS
RADIOISOTOPES
REACTOR COMPONENTS
REACTOR CORES
REACTOR PHYSICS
RESONANCE INTEGRALS
SELF-SHIELDING
SHIELDING
SLIGHTLY ENRICHED URANIUM
SPONTANEOUS FISSION RADIOISOTOPES
TEMPERATURE DEPENDENCE
URANIUM
URANIUM 235
URANIUM ISOTOPES
US AEC
US DOE
US ERDA
US ORGANIZATIONS