Delayed-neutron spectral calculation using augmented ENDF/B-V data
Technical Report
·
OSTI ID:5161652
We have used the evaluated nuclear data files (ENDF/B-V) for 105 precursors, augmented with experimental spectral data for 29 emitters and recent model calculations for the remaining 76 emitters, in aggregate summation calculations. The equilibrium delayed neutrons and spectra in the conventional six time-groups for 11 fissionable nuclides were calculated. Normalized experimental emitter spectra for 29 emitters were supplied by G. Rudstam. Augmentation of the spectra uses data calculated with a recently developed code, BETA. Fission yields of the precursors and their Pn values are from ENDF/B-V. Results are compared where possible with corresponding group and total evaluations of aggregate measurements. The intent of these calculations is to examine the adequacy of data for inclusion in ENDF/B-VI. Most of the results, particularly with the added model parameters, are sufficiently accurate to be of direct interest to the reactor community. The total /anti/nu/sub d/ values for /sup 238/U and /sup 232/Th suggest that either an improvement in fission yields is needed or the evaluated experimental /anti/nu/sub d/ values are in significant error.
- Research Organization:
- Hanford Engineering Development Lab., Richland, WA (USA); Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- AC06-76FF02170; W-7405-ENG-36
- OSTI ID:
- 5161652
- Report Number(s):
- HEDL-SA-2632-FP; LA-UR-82-78; CONF-820609-68; ON: DE82018945
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
651713* -- Nuclear Properties & Reactions
A=90-149
Theoretical-- Energy Levels & Transitions-- (-1987)
652016 -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
DATA
DATA COMPILATION
DELAYED NEUTRON PRECURSORS
DELAYED NEUTRONS
ELEMENTARY PARTICLES
FERMIONS
FISSION
FISSION NEUTRONS
FISSION PRODUCTS
FISSION YIELD
HADRON REACTIONS
HADRONS
INFORMATION
ISOTOPES
MATERIALS
MULTIPLICITY
NEUTRON REACTIONS
NEUTRON SPECTRA
NEUTRONS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
RADIOACTIVE MATERIALS
RADIOISOTOPES
SPECTRA
TARGETS
THEORETICAL DATA
THORIUM 232 TARGET
URANIUM 238 TARGET
YIELDS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
651713* -- Nuclear Properties & Reactions
A=90-149
Theoretical-- Energy Levels & Transitions-- (-1987)
652016 -- Nuclear Properties & Reactions
A=220 & above
Theoretical-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
DATA
DATA COMPILATION
DELAYED NEUTRON PRECURSORS
DELAYED NEUTRONS
ELEMENTARY PARTICLES
FERMIONS
FISSION
FISSION NEUTRONS
FISSION PRODUCTS
FISSION YIELD
HADRON REACTIONS
HADRONS
INFORMATION
ISOTOPES
MATERIALS
MULTIPLICITY
NEUTRON REACTIONS
NEUTRON SPECTRA
NEUTRONS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
NUMERICAL DATA
RADIOACTIVE MATERIALS
RADIOISOTOPES
SPECTRA
TARGETS
THEORETICAL DATA
THORIUM 232 TARGET
URANIUM 238 TARGET
YIELDS