Published 1981
| Version v1
Journal article
Post irradiation analysis of BWR and PWR fuel samples: experimental results and their interpretation
Description
The Joint Research Center (JRC) of the Commission of the European Communities (CEC) has carried out for many years destructive post irradiation analysis of samples from BWR and PWR fuel elements. A total of about 120 pellets with a burnup range from 3.5 to 37.5 GWD/MTU have been investigated. The main goal was to create a bank of qualified data on burnup and isotope buildup of spent fuels, to be used in the assessment of some Safeguards techniques. This report presents a summary of the latest results of this activity, together with a discussion and a comparison between measured and calculated data. 18 refs
Additional details
Publishing Information
- Journal Title
- Nucl. Mater. Manage.
- Journal Volume
- 10
- Series
- Nucl. Mater. Manage.
- Journal Page Range
- 90-94
Conference
- Title
- Institute of Nuclear Materials Management conference.
- Dates
- 13 Jul 1981.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 14719022
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S98: NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; BWR TYPE REACTORS; PWR TYPE REACTORS; SPENT FUELS
- Descriptors DEC
- ENERGY SOURCES; FUELS; MATERIALS; NUCLEAR FUELS; REACTOR MATERIALS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-810706--.