Monte Carlo analysis of direct measurements of the fission neutron yield per absorption by /sup 233/U and /sup 235/U of monochromatic neutrons
Journal Article
·
· Nucl. Sci. Eng.; (United States)
OSTI ID:7340983
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 /sup 233/U and /sup 235/U yields: eta/sub 2200//sup 233/ = 2.2993 +- 0.0082 and eta/sub 2200//sup 235/ = 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 eta/sub 2200/.
- Research Organization:
- Bettis Atomic Power Lab., West Mifflin, PA
- OSTI ID:
- 7340983
- Journal Information:
- Nucl. Sci. Eng.; (United States), Journal Name: Nucl. Sci. Eng.; (United States) Vol. 60:3; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Monte Carlo analysis of thermal-spectrum averaged measurements of eta of /sup 233/U and /sup 235/U
Monte Carlo analysis of manganese bath measurements of eta of /sup 233/U and /sup 235/U using thermalized neutrons
Monte Carlo analysis of direct measurements of the thermal eta (0. 025 eV) for /sup 233/U and /sup 235/U (LWBR Development Program)
Journal Article
·
Thu Jul 01 00:00:00 EDT 1976
· Nucl. Sci. Eng.; (United States)
·
OSTI ID:7264961
Monte Carlo analysis of manganese bath measurements of eta of /sup 233/U and /sup 235/U using thermalized neutrons
Conference
·
Wed Oct 01 00:00:00 EDT 1975
· Natl. Bur. Stand. (U.S.), Spec. Publ.; (United States)
·
OSTI ID:7362254
Monte Carlo analysis of direct measurements of the thermal eta (0. 025 eV) for /sup 233/U and /sup 235/U (LWBR Development Program)
Technical Report
·
Tue Apr 01 00:00:00 EDT 1975
·
OSTI ID:6731556
Related Subjects
652026* -- Nuclear Properties & Reactions
A=220 & above
Experimental-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
CROSS SECTIONS
ELEMENTARY PARTICLES
FERMIONS
FISSION
FISSION NEUTRONS
FISSION YIELD
HADRON REACTIONS
HADRONS
MONTE CARLO METHOD
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
TARGETS
THERMAL FISSION
URANIUM 233 TARGET
URANIUM 235 TARGET
YIELDS
A=220 & above
Experimental-- Spontaneous & Induced Fission-- (-1987)
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
BARYON REACTIONS
BARYONS
CROSS SECTIONS
ELEMENTARY PARTICLES
FERMIONS
FISSION
FISSION NEUTRONS
FISSION YIELD
HADRON REACTIONS
HADRONS
MONTE CARLO METHOD
NEUTRON REACTIONS
NEUTRONS
NUCLEAR REACTION YIELD
NUCLEAR REACTIONS
NUCLEON REACTIONS
NUCLEONS
TARGETS
THERMAL FISSION
URANIUM 233 TARGET
URANIUM 235 TARGET
YIELDS