Review of spent-fuel photon and neutron source spectra

Technical Report · Wed Jan 01 00:00:00 EST 1986

DOI:https://doi.org/10.2172/6234717· OSTI ID:6234717

Hermann, O W; Alexander, C W

The calculations of spent-fuel photon and neutron spectra have been significantly improved over the past several years. Methods for performing these computations at ORNL have been implemented in the ORIGEN2 and ORIGEN-S codes and the SAS2 control module of the SCALE system. The codes use photon data for delayed gamma rays, x-rays, spontaneous fission gamma rays, (..cap alpha..,n) reaction gamma rays, bremsstrahlung and decay constants, taken mainly from the Evaluated Nuclear Data Structure File. The data for neutron source strengths and spectral distributions of spontaneous fission and (..cap alpha..,n) reactions were compiled from several different research projects. Brief discussions of the codes, the spectral data and the range of applicability are presented. Also, several examples of spent-fuel photon and neutron spectra are included. 29 refs.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6234717
• Report Number(s): ORNL/CSD/TM-205; ON: DE86006764
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
SPENT FUELS
GAMMA SPECTRA
ISOTOPE RATIO
NEUTRON SPECTRA
BREMSSTRAHLUNG
GAMMA RADIATION
GAMMA SOURCES
NEUTRON SOURCES
X-RAY SOURCES
ELECTROMAGNETIC RADIATION
ENERGY SOURCES
EQUIPMENT
FUELS
IONIZING RADIATIONS
MATERIALS
NUCLEAR FUELS
PARTICLE SOURCES
RADIATION SOURCES
RADIATIONS
REACTOR MATERIALS
SPECTRA
X-RAY EQUIPMENT
050800* - Nuclear Fuels- Spent Fuels Reprocessing