Analysis of PROTEUS phase II experiments performed using the AARE modular system and JEF-based libraries
Journal Article
·
· Nuclear Science and Engineering; (USA)
OSTI ID:7038145
- Paul Scherrer Inst. (PSI), Wuerenlingen (Switzerland)
The capability of the advanced analysis of reactor engineering (AARE) modular code system and JEF-1-based nuclear data libraries to analyze light water high converter reactor (LWHCR) lattices is investigated by calculating the wet and dry cells of the PROTEUS-LWHCR phase II experiment. The results are compared to those obtained using several cell codes. Main features of the AARE code system, such as the self-shielding of resonance cross sections in the whole energy range, the generation of adequate fission source spectra, and the efficiency of the elastic removal correction,are investigated. In particular, it is shown that AARE results for the k {infinity} void coefficient agree very well with the experiment, whereas other codes give larger deviations.
- OSTI ID:
- 7038145
- Journal Information:
- Nuclear Science and Engineering; (USA), Journal Name: Nuclear Science and Engineering; (USA) Vol. 103:3; ISSN 0029-5639; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
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Investigation of the void coefficient and other integral parameters in the PROTEUS-LWHCR phase II program
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Journal Article
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Sun Jan 31 23:00:00 EST 1988
· Nucl. Technol.; (United States)
·
OSTI ID:7226978
A one- and two-dimensional cross-section sensitivity and uncertainty path of the AARE (Advanced Analysis for Reactor Engineering) modular code system
Conference
·
Thu Dec 31 23:00:00 EST 1987
·
OSTI ID:6720902
Comparative analysis of the reference GCFR-PROTEUSMOX lattice with MCNPX-15e and ERANOS-2.0 in conjunction with modern nuclear data libraries
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Sat Jul 01 00:00:00 EDT 2006
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OSTI ID:22039530
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
DATA ACQUISITION
ENGINEERING
ENRICHED URANIUM REACTORS
FISSION SPECTRA
GRAPHITE MODERATED REACTORS
MODULAR STRUCTURES
NUCLEAR ENGINEERING
PROTEUS REACTOR
REACTIVITY COEFFICIENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SPECTRA
TEST REACTORS
VOID COEFFICIENT
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
220900* -- Nuclear Reactor Technology-- Reactor Safety
COMPUTER CODES
DATA ACQUISITION
ENGINEERING
ENRICHED URANIUM REACTORS
FISSION SPECTRA
GRAPHITE MODERATED REACTORS
MODULAR STRUCTURES
NUCLEAR ENGINEERING
PROTEUS REACTOR
REACTIVITY COEFFICIENTS
REACTOR SAFETY EXPERIMENTS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SPECTRA
TEST REACTORS
VOID COEFFICIENT