Published July 1976
| Version v1
Journal article
Monte Carlo analysis of direct measurements of the fission neutron yield per absorption by 233U and 235U of monochromatic neutrons
Description
Monte Carlo analysis of the measurements of Smith et al. of the number of fission neutrons produced per neutron absorbed, eta, for 2200 m/sec neutrons absorbed by 233U and 235U yields: eta2200233 = 2.2993 +- 0.0082 and eta2200235 = 2.0777 +- 0.0064. The standard deviations include Monte Carlo, cross section, and experimental uncertainties. The Monte Carlo analysis was confirmed by calculating measured quantities used by the experimentalists in determining eta2200
Additional details
Identifiers
Publishing Information
- Journal Title
- Nuclear Science and Engineering
- Journal Volume
- 60
- Journal Issue
- 3
- Series
- Nucl. Sci. Eng.
- Journal Page Range
- 239-250
- ISSN
- 0029-5639
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 8285888
- Subject category
- S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
- Descriptors DEI
- CROSS SECTIONS; FISSION NEUTRONS; FISSION YIELD; MONTE CARLO METHOD; NEUTRON REACTIONS; THERMAL FISSION; URANIUM 233 TARGET; URANIUM 235 TARGET
- Descriptors DEC
- BARYON REACTIONS; BARYONS; ELEMENTARY PARTICLES; FERMIONS; FISSION; HADRON REACTIONS; HADRONS; NEUTRONS; NUCLEAR REACTION YIELD; NUCLEAR REACTIONS; NUCLEON REACTIONS; NUCLEONS; TARGETS
Optional Information
- Notes
- Updated automatically by Metadata and Full-Text Enrichment Agent