Study Of Core Conversion To A Mixed Core Of HEU And LEU For The Dalat Nuclear Research Reactor
- 1. Nuclear Research Institute, Dalat (Viet Nam)
Description
This paper presents the results of design and safety analysis performed in the framework of R-D project of Ministry of Science and Technology for inserting either 36 fresh HEU VVR-M2 (36% enrichment, 3 tubes, U-Al alloy fuel meat 1.40 g U/cm3 and 40.2 g 235U) fuel assemblies currently on-hand at the Dalat Nuclear Research Reactor (DNRR) or 36 LEU VVR-M2 (19.75% enrichment, 3 tubes, UO2-Al fuel meat 2.50 g U/cm3 and 49.7 g 235U) fuel assemblies to be procured when additional reactivity is required for continued operation around April 2006. The design and safety analyses presented in this report provide comparisons of neutronic parameters (fuel-cycle length, power distribution, neutron flux distribution, excess reactivity, shutdown margins, kinetics parameters), thermal-hydraulic safety margins and accident analyses (reactivity insertion transient analyse, maximum positive reactivity insertion, fuel cladding failure) for reloaded cores using 36 additional HEU VVR-M2 or 36 LEU VVR-M2 fuel assemblies in the DNRR. These results of analyses obtained enable to reach the conclusion that it is feasible to replace the current HEU VVR-M2 fuel assemblies with LEU VVR-M2 fuel assemblies that are fully qualified and have been commercially available since 2001 from the Novosibirsk Chemical Concentrates Plant in Russia. (author)
Additional details
Additional titles
- Original title (Vietnamese)
- Nghien cuu chuyen doi vung hoat lo phan ung hat nhan Dalat sang su dung hon hop voi nhien lieu do giau thap
Publishing Information
- Publisher
- Science and Technics Publishing House
- Imprint Place
- Hanoi (Viet Nam)
- Imprint Title
- Proceedings of the 7"t"h National Conference on Nuclear Science and Technology
- Imprint Pagination
- 703 p.
- Journal Page Range
- p. 124-130
INIS
- Country of Publication
- Viet Nam
- Country of Input or Organization
- Viet Nam
- INIS RN
- 40107570
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- COMPUTER CODES; DESIGN; FUEL ASSEMBLIES; FUEL CYCLE; KINETICS; MODERATELY ENRICHED URANIUM; NEUTRON FLUX; POWER DISTRIBUTION; REACTIVITY; REACTIVITY INSERTIONS; SAFETY ANALYSIS; SAFETY MARGINS; SLIGHTLY ENRICHED URANIUM; TRANSIENTS; TRIGA-2-DALAT REACTOR
- Descriptors DEC
- ACTINIDES; ELEMENTS; ENRICHED URANIUM; ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE ENRICHED MATERIALS; ISOTOPE PRODUCTION REACTORS; MATERIALS; METALS; RADIATION FLUX; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS