MEASUREMENT OF FISSION NEUTRON FLUXES AND SPECTRA WITH THRESHOLD DETECTORS

Technical Report · Fri May 15 04:00:00 EDT 1964

OSTI ID:4037079

Roy, J. C.; Durham, R. W.; Fowler, A. G.; Hawton, J. J.

The spectral shape of the neutron flux above ~0.5 MeV in the D2O moderated reactor NRX has been investigated because of its importance in studies of irradiation damage, reactor shielding and fast fission of reactor fuel. The deviations from a pure fission flux over the energy sensitive regions of several threshold reactions have been measured for several irradiation positions. A hollow natural uranium rod in a beam hole was used as a fission neutron source and the reaction Ni-58(n,p) was used to normalize each irradiation. The results for an empty lattice position have been used to compute the spectrum in this position assuming the shape can be expressed by the equation specified.. This is the equation of Cranberg et al, for a pure fission spectrum with B and v as spectral parameters determined from the threshold reaction rates.

• Research Organization: Atomic Energy of Canada Ltd., Chalk River, Ontario (Canada)
• NSA Number: NSA-18-035836
• OSTI ID: 4037079
• Report Number(s): CRC-1101; AECL-1994
• Country of Publication: Canada
• Language: English

Related Subjects

COBALT 58
CONFIGURATION
ENERGY
FAST NEUTRONS
FISSION
FUEL ELEMENTS
FUELS
HEAVY WATER MODERATOR
INSTRUMENTATION
IRRADIATION
MEASURED VALUES
NATURAL URANIUM FUEL
NEUTRON FLUX
NEUTRON SOURCES
NEUTRONS
NICKEL 58
NRX
NUCLEAR REACTIONS
NUMERICALS
PROTONS
RADIATION DETECTORS
RADIATION EFFECTS
REACTORS
RODS
SHIELDING
SPECTRA
THRESHOLD DETECTORS
USES