Methods/data testing for advanced LWR fuel designs and operational modes in the PROTEUS facility
Creators
- 1. Paul Scherrer Institute, Villigen PSI (Switzerland)
Description
In the framework of the LWR-PROTEUS programme, integral experiments are being performed for the validation of reactor physics methods/data applied to the analysis of modern light water (LWR) fuel assembly designs. One of the important aspects pertaining to this programme is the investigation of the sensitivity of integral quantities, such as reaction rate spatial distributions, local reaction rate ratios and reactivity effects, to different nuclear data sets, e.g. ENDF/B-V, ENDF/B-VI and JEF-2.2. Data sensitivity studies are currently reported, largely based on continuous-energy Monte Carlo calculations at PROTEUS-core, BWR fuel assembly and pin-cell levels. Data effects could thus be investigated systematically, independent of the inherent limitations of deterministic codes such as geometrical simplification and resonance shielding approximations. The results show a significant sensitivity of system reactivity to the data set employed, calculated values being larger by several hundreds of pcm with JEF-2.2 than with ENDF/B-V or B-VI. As regards detailed reaction rate distributions in BWR assemblies (investigated in LWR-PROTEUS Phase I), there appears to be only a weak dependence on the data library used. In the context of the investigations planned with highly burnt fuel rod segments in the Phase II experiments, certain studies made at pin-cell level have indicated that the effects of basic data differences are likely to be much lower than uncertainties in fuel composition predictions. (author)
Availability note (English)
Available from the Internet at URL https://doi.org/10.1080/00223131.2002.10875181Additional details
Identifiers
Publishing Information
- Publisher
- Atomic Energy Society of Japan
- Imprint Place
- Tokyo (Japan)
- Imprint Title
- Proceedings of the international conference on nuclear data for science and technology
- Imprint Pagination
- 1547 p.
- Journal Page Range
- p. 642-645
Conference
- Title
- International conference on nuclear data for science and technology
- Acronym
- ND 2001
- Dates
- 7-12 Oct 2001
- Place
- Tsukuba, Ibaraki (Japan)
INIS
- Country of Publication
- Japan
- Country of Input or Organization
- Japan
- INIS RN
- 51063263
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CONTROL ROD WORTHS; DATA ANALYSIS; FUEL ASSEMBLIES; MONTE CARLO METHOD; NUCLEAR DATA COLLECTIONS; PROTEUS REACTOR; REACTION KINETICS; REACTIVITY; REACTOR KINETICS; URANIUM DIOXIDE
- Descriptors DEC
- ACTINIDE COMPOUNDS; CALCULATION METHODS; CHALCOGENIDES; DATA PROCESSING; ENRICHED URANIUM REACTORS; GRAPHITE MODERATED REACTORS; KINETICS; OXIDES; OXYGEN COMPOUNDS; PROCESSING; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; TEST FACILITIES; TEST REACTORS; URANIUM COMPOUNDS; URANIUM OXIDES
Optional Information
- Notes
- 8 refs., 3 figs., 4 tabs.; This record replaces 34024812 Imprint:Published as supplement 2 of Journal of Nuclear Science and Technology in 2 volumes