Interpretation of TRIGA reactivity transients with RELAP5/PARCS coupled-code
Creators
- 1. Italian National Agency for New Technologies Energy and the Environment, 4 Via Martin di Monte Sole, 40129 Bologna (Italy)
Description
In the frame of future experiments to carried out upon TRIGA reactors, which aim to verify the real feasibility of the ADS (Accelerator Driven System) concept, it is essential to build a numerical tool able to simulate the dynamic behaviour of the reactor in subcritical configuration. This model developed to support the design of subcritical experiments and the safety analysis of the reactor, as a first step has to be assessed against the experimental data available for the critical reactor. To this purpose the thermal-hydraulic/ neutronic numerical model based on the RELAP5/PARCS coupled-code is been tested against the experimental reactivity transients conducted on the RC1-TRIGA reactor at the ENEA Casaccia Research Center in forecast of the TRADE (TRIGA Accelerator Driven Experiment) subcritical experience. The results of the calculations already performed show a qualitative good agreement with the experimental data and allow to address the future developments and improvements of the numerical model. (authors)
Additional details
Publishing Information
- Publisher
- American Nuclear Society - ANS
- Imprint Place
- La Grange Park (United States)
- ISBN
- 0-89448-697-7
- Imprint Pagination
- 9 p.
Conference
- Title
- American Nuclear Society's Topical Meeting on Reactor Physics - Advances in Nuclear Analysis and Simulation
- Acronym
- PHYSOR-2006
- Dates
- 10-14 Sep 2006
- Place
- Vancouver, BC (Canada)
INIS
- Country of Publication
- United States
- Country of Input or Organization
- France
- INIS RN
- 43129832
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- DESIGN; EXPERIMENTAL DATA; NEA; P CODES; R CODES; REACTIVITY; REACTIVITY COEFFICIENTS; REACTOR KINETICS; SAFETY ANALYSIS; THERMAL HYDRAULICS; TRIGA-2-ROME REACTOR
- Descriptors DEC
- COMPUTER CODES; DATA; ENRICHED URANIUM REACTORS; FLUID MECHANICS; HOMOGENEOUS REACTORS; HYDRAULICS; HYDRIDE MODERATED REACTORS; INFORMATION; INTERNATIONAL ORGANIZATIONS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; KINETICS; MECHANICS; NUMERICAL DATA; OECD; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs.