Published July 1976 | Version v1
Journal article Metadata-only

Monte Carlo analysis of thermal-spectrum averaged measurements of eta of 233U and 235U

Creators

  • 1. Bettis Atomic Power Lab., West Mifflin, PA

Description

Monte Carlo analysis of the Oak Ridge National Laboratory measurements of the fission neutron yield due to the absorption of a 2200 m/sec neutron in 233U and 235U, respectively, yields: eta2200233 = 2.3019 +- 0.0086 and eta2200235 = 2.0746 +- 0.0078. The analysis was confirmed by calculating measured quantities employed by the experimentalists in their determinations of eta2200

Additional details

Identifiers

DOI
10.13182/nse76-a26882;

Publishing Information

Journal Title
Nuclear Science and Engineering
Journal Volume
60
Journal Issue
3
Series
Nucl. Sci. Eng.
Journal Page Range
251-261
ISSN
0029-5639

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
8285793
Subject category
S73: NUCLEAR PHYSICS AND RADIATION PHYSICS;
Descriptors DEI
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
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