Published January 1984
| Version v1
Report
Restricted
ORIGEN2 calculations of PWR [pressurized water reactor] spent fuel decay heat compared with calorimeter measurements
Description
Decay heat generation rates calculated with the ORIGEN2 code are compared with measured calorimetric values for 19 spent fuel assemblies from three commercial pressurized water reactors. The agreement is typically 5% or better. The sensitivity of the calculations to the required input data is investigated and the key parameters are identified
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE87009517.
Files
Restricted
The record is publicly accessible, but files are restricted to users with access.
Additional details
Publishing Information
- Imprint Pagination
- 6 p.
- Report number
- HEDL-SA--3086
Conference
- Title
- ANS International topical meeting on fuel reprocessing and waste management.
- Dates
- 26-29 Aug 1984.
- Place
- Jackson Hole, WY (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18095531
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; CALORIMETRY; COMPUTER CALCULATIONS; FUEL ASSEMBLIES; O CODES; PWR TYPE REACTORS; SPENT FUELS; TESTING
- Descriptors DEC
- COMPUTER CODES; ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-840802--32.