Evaluation of spent fuel isotopics, radiation spectra and decay heat using the scale computational system

Conference · Tue Dec 31 23:00:00 EST 1985

OSTI ID:5369296

Parks, C V; Hermann, O W; Ryman, J C

In order to be a self-sufficient system for transport/storage cask shielding and heat transfer analysis, the SCALE system developers included modules to evaluate spent fuel radiation spectra and decay heat. The primary module developed for these analyses is ORIGEN-S which is an updated verision of the original ORIGEN code. The COUPLE module was also developed to enable ORIGEN-S to easily utilize multigroup cross sections and neutron flux data during a depletion analysis. Finally, the SAS2 control module was developed for automating the depletion and decay via ORIGEN-S while using burnup-dependent neutronic data based on a user-specified fuel assembly and reactor history. The ORIGEN-S data libraries available for depletion and decay have also been significantly updated from that developed with the original ORIGEN code.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5369296
• Report Number(s): CONF-8606146-3; ON: TI86015924
• Country of Publication: United States
• Language: English

Related Subjects

050900* -- Nuclear Fuels-- Transport
Handling
& Storage
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
AFTER-HEAT
COMPUTER CODES
COMPUTERIZED SIMULATION
ENERGY TRANSFER
FUEL ELEMENTS
HEAT TRANSFER
ISOTOPE RATIO
REACTOR COMPONENTS
S CODES
SIMULATION
SOURCE TERMS
SPENT FUEL ELEMENTS