Published 1998
| Version v1
Report
Investigation of burnup dependent radial power distributions for highly enriched Halden test pins by the spectral code CIRTHE
Creators
Description
CIRTHE is a one-dimensional collision probability method with burnup. Although primarily written for heavy water fuel rod cluster calculations, it can also be applied to light water moderated fuel lattices. CIRTHE calculations on PWR and BWR fuel rods have been checked against experiments involving capture rates of heavy nuclides, fuel temperature coefficients at full power conditions, relative concentrations of U- and Pu-isotopes in burnt fuel assemblies as well as xenon reactivities. A very satisfactory agreement between calculations and experiments was obtained. CIRTHE is well suited for application to HBWR conditions. Results of the analysis of ultra high burnup rig rods are presented. (author)
Additional details
Publishing Information
- Imprint Title
- High burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
- Imprint Pagination
- [vp.]
- Journal Page Range
- [10 p.]
- Report number
- HPR--349
Conference
- Title
- Enlarged Halden programme group meeting on high burn-up fuel performance, safety and reliability and degradation of in-core materials and water chemistry effects and man-machine systems research
- Dates
- 15-20 Mar 1998
- Place
- Lillehammer (Norway)
INIS
- Country of Publication
- Norway
- Country of Input or Organization
- Norway
- INIS RN
- 35048557
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- BURNUP; ENERGY; HBWR REACTOR; INSPECTION; INTERNATIONAL COOPERATION; MAN-MACHINE SYSTEMS; NUCLEAR FUELS; OECD; PWR TYPE REACTORS; REACTOR MAINTENANCE; REACTOR SAFETY; RELIABILITY; WATER CHEMISTRY
- Descriptors DEC
- BHWR TYPE REACTORS; CHEMISTRY; COOPERATION; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; HEAVY WATER COOLED REACTORS; HEAVY WATER MODERATED REACTORS; INTERNATIONAL ORGANIZATIONS; MAINTENANCE; MATERIALS; POWER REACTORS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; TANK TYPE REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 8 refs., 10 figs.
- Secondary number(s)
- HPR--349/31