Published 1984
| Version v1
Book
ORIGEN2 calculations of PWR 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
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- LaGrange Park, IL (USA)
- Imprint Title
- Fuel reprocessing and waste management. Volume 2
- Journal Page Range
- p. 69-74.
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
- 17049742
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT; CALORIMETERS; CALORIMETRY; COMPUTER CODES; O CODES; PWR TYPE REACTORS; SENSITIVITY; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; MATERIALS; MEASURING INSTRUMENTS; NUCLEAR FUELS; POWER REACTORS; REACTOR MATERIALS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS