Utilization of ORIGEN2 by the characteristics data base
The radiological characteristics in the Characteristic Data Base (CDB) are calculated using the ORIGEN2 code. Several significant near-term improvements in the application of the code have been incorporated in application of the code have been incorporated in calculations for Revision 1 of the CDB. First, revised ORIGEN2 pressurized-water reactor (PWR) and boiling-water reactor (BWR) cross section libraries were used. Second, enrichment was adjusted for each burnup and the combinations of enrichment and burnup used encompass most of the projected spent-fuel population. Finally, reactor cycle parameters that more closely match recent and anticipated utility practice were used. In this paper we discuss the motivation for these improvements, describe their implementation, present a sample of significant results, and explore limitations.
- Research Organization:
- Oak Ridge National Lab., TN (United States)
- Sponsoring Organization:
- USDOE; USDOE, Washington, DC (United States)
- DOE Contract Number:
- AC05-84OR21400
- OSTI ID:
- 5785699
- Report Number(s):
- CONF-920430-49; ON: DE92007243
- Resource Relation:
- Conference: International high level radioactive waste management (IHLRWM) conference: promoting understanding through education and communication, Las Vegas, NV (United States), 12-16 Apr 1992
- Country of Publication:
- United States
- Language:
- English
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BURNUP
O CODES
SPENT FUELS
BWR TYPE REACTORS
DATA BASE MANAGEMENT
ENRICHMENT
HIGH-LEVEL RADIOACTIVE WASTES
PWR TYPE REACTORS
COMPUTER CODES
ENERGY SOURCES
ENRICHED URANIUM REACTORS
FUELS
MANAGEMENT
MATERIALS
NUCLEAR FUELS
POWER REACTORS
RADIOACTIVE MATERIALS
RADIOACTIVE WASTES
REACTOR MATERIALS
REACTORS
THERMAL REACTORS
WASTES
WATER COOLED REACTORS
WATER MODERATED REACTORS
052001* - Nuclear Fuels- Waste Processing