Core Management of the Dalat Nuclear Research Reactor
- 1. Nuclear Research Institute, Dalat (Viet Nam)
Description
The Dalat nuclear research reactor (DNRR) is a pool-type research reactor which was reconstructed from the 250 kW TRIGA-MARK II reactor. The reconstructed reactor reached its initial criticality in November 1983 and attained its nominal power of 500 kW in February 1984. The DNRR uses Russian fuel assemblies, type WWR-SM. The first fuel reloading was executed in April 1994 after more than ten years of operation with 89 fuel assemblies. Research on core management of DNRR with the purpose of maintaining safe operation and effective utilization of reserve fuel assem- blies is being carried out at the Nuclear Research Institute. Calculations of fuel burn-up for the Dalat nuclear research reactor are carried out based on the cell calculation program WIMS and two diffusion calculation programs HEXAGA and HEXNOD. Experimental measurement of fuel burn-up for the Dalat nuclear research reactor was realized by a measurement method of long-life isotopes from fission products. Optimum second fuel reloading and future refuelling for DNRR have been gained. A second fuel reloading for the Dalat nuclear research reactor was realized in March 2002. After reloading the working configuration of the reactor, the core consisted of 104 fuel assemblies. Research results for future refuelling for DNRR show that with 36 reserve fuel assemblies, the reactor will be operated for at least 17 851 h at nominal power since the second fuel reloading. (author)
Additional details
Identifiers
Publishing Information
- Publisher
- IAEA
- Imprint Place
- Vienna (International Atomic Energy Agency (IAEA))
- ISBN
- 92-0-113904-7
- Imprint Title
- Research Reactor Utilization, Safety, Decommissioning, Fuel and Waste Management. Proceedings of an International Conference
- Imprint Pagination
- 732 p.
- Series
- Proceedings Series
- Journal Page Range
- p. 429-439
- ISSN
- 0074-1884
Conference
- Title
- International Conference on Research Reactor Utilization, Safety, Decommissioning, Fuel and Waste Management
- Dates
- 10-14 Nov 2003
- Place
- Santiago (Chile)
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 43080918
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BURNUP; CONFIGURATION; CRITICALITY; FISSION PRODUCTS; FUEL ASSEMBLIES; MANAGEMENT; OPERATION; RESEARCH REACTORS; TRIGA-2 REACTOR; TRIGA-2-DALAT REACTOR
- Descriptors DEC
- ENRICHED URANIUM REACTORS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; THERMAL REACTORS; TRIGA TYPE REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 7 figs., 1 tab., 3 refs.
- Secondary number(s)
- IAEA-CN--100/134