Comparison of radiation sources from selected point depletion codes
Conference
·
· Transactions of the American Nuclear Society; (USA)
OSTI ID:5580028
- Oak Ridge National Lab., TN (USA)
Three radionuclide inventory/depletion codes, ORIGEN2, ORIGEN-S, and CINDER-2, were chosen to be used in a study to compare and to assess the performance of both neutron and photon source spectra in a shielding analysis of a typical spent-fuel cask. The comparisons were made for a series of five test cases involving light water reactor (LWR) models (three pressurized water reactors (PWRs) and two boiling water reactors (BWRs)) at cooling times ranging from 30 days to 50 yr. The results of this comparison of photon and neutron source strengths and the application of the source spectra in a typical shielding problem suggest that the differences among the three codes may be attributed to differences in the data libraries and not in the methodology applied in each of these codes.
- OSTI ID:
- 5580028
- Report Number(s):
- CONF-881011--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (USA) Journal Volume: 57
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparison of radiation spectra from selected source-term computer codes
Multicode comparison of selected source-term computer codes
ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
Technical Report
·
Fri Mar 31 23:00:00 EST 1989
·
OSTI ID:6218812
Multicode comparison of selected source-term computer codes
Technical Report
·
Fri Mar 31 23:00:00 EST 1989
·
OSTI ID:6225635
ORIGEN2: A versatile computer code for calculating the nuclide compositions and characteristics of nuclear materials
Journal Article
·
Thu Sep 01 00:00:00 EDT 1983
· Nucl. Technol.; (United States)
·
OSTI ID:6475959
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BURNUP
BWR TYPE REACTORS
C CODES
CASKS
COMPUTER CODES
CONTAINERS
ELEMENTARY PARTICLES
GE STANDARD REACTOR
INVENTORIES
ISOTOPES
MASSLESS PARTICLES
NEUTRON FLUX
NEUTRON SOURCES
O CODES
PARTICLE SOURCES
PERFORMANCE
PHOTONS
PWR TYPE REACTORS
RADIATION FLUX
RADIATION SOURCES
RADIOISOTOPES
REACTORS
SHIELDING
SOURCE TERMS
SPENT FUEL CASKS
SPENT FUEL STORAGE
STORAGE
TIME DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BURNUP
BWR TYPE REACTORS
C CODES
CASKS
COMPUTER CODES
CONTAINERS
ELEMENTARY PARTICLES
GE STANDARD REACTOR
INVENTORIES
ISOTOPES
MASSLESS PARTICLES
NEUTRON FLUX
NEUTRON SOURCES
O CODES
PARTICLE SOURCES
PERFORMANCE
PHOTONS
PWR TYPE REACTORS
RADIATION FLUX
RADIATION SOURCES
RADIOISOTOPES
REACTORS
SHIELDING
SOURCE TERMS
SPENT FUEL CASKS
SPENT FUEL STORAGE
STORAGE
TIME DEPENDENCE
WATER COOLED REACTORS
WATER MODERATED REACTORS
WESTINGHOUSE STANDARD REACTOR