Computational analysis of irradiation facilities at the JSI TRIGA reactor
Creators
- 1. Jožef Stefan Institute, Jamova cesta 39, SI-1000 Ljubljana (Slovenia)
Description
Characterization and optimization of irradiation facilities in a research reactor is important for optimal performance. Nowadays this is commonly done with advanced Monte Carlo neutron transport computer codes such as MCNP. However, the computational model in such calculations should be verified and validated with experiments. In the paper we describe the irradiation facilities at the JSI TRIGA reactor and demonstrate their computational characterization to support experimental campaigns by providing information on the characteristics of the irradiation facilities. - Highlights: ► TRIGA reactor at JSI suitable for irradiation under well defined conditions. ► It features irradiation channels of different fluxes, spectra, and dimensions. ► Computational model has been developed and experimentally verified. ► The model used for optimization of experiments and evaluation of uncertainties.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.apradiso.2011.11.042Additional details
Identifiers
- DOI
- 10.1016/j.apradiso.2011.11.042;
- PII
- S0969-8043(11)00596-3;
Publishing Information
- Journal Title
- Applied Radiation and Isotopes
- Journal Volume
- 70
- Journal Issue
- 3
- Journal Page Range
- p. 483-488
- ISSN
- 0969-8043
- CODEN
- ARISEF
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43072938
- Subject category
- S07: ISOTOPES AND RADIATION SOURCES;
- Descriptors DEI
- COMPUTER CODES; EVALUATION; IRRADIATION; IRRADIATION PLANTS; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON TRANSPORT; OPTIMIZATION; PERFORMANCE; RESEARCH REACTORS; SPECTRA; TRIGA TYPE REACTORS
- Descriptors DEC
- CALCULATION METHODS; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; NEUTRAL-PARTICLE TRANSPORT; NUCLEAR FACILITIES; RADIATION FLUX; RADIATION TRANSPORT; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2011 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.