Burnup analysis and in-core fuel management study of the 3 MW TRIGA MARK II research reactor
Creators
- 1. Institute of Nuclear Science and Technology Atomic Energy Research Establishment Ganakbari, Savar, GPO Box 3787, Dhaka 1000 (Bangladesh)
- 2. Research Laboratory for Nuclear Reactors, Tokyo Institute of Technology, 2-12-1-N1-19 Ookayama, Meguro-ku, Tokyo 152-8550 (Japan)
Description
The principal objective of this study is to formulate an effective optimal fuel management strategy for the TRIGA MARK II research reactor at AERE, Savar. The core management study has been performed by utilizing four basic types of information calculated for the reactor: criticality, power peaking, neutron flux and burnup calculation. This paper presents the results of the burnup calculations for TRIGA LEU fuel elements. The fuel element burnup for approximately 20 years of operation was calculated using the TRIGAP compute code. The calculation is performed in one-dimensional radial geometry in TRIGAP. Inter-comparison of TRIGAP results with other two calculations performed by MVP-BURN and MCNP4C-ORIGEN2.1 show very good agreement. Reshuffling at 20,000 MWh step provides the highest core lifetime of the reactor, which is 64,500 MWh. Besides, the study gives valuable insight into the behaviour of the reactor and will ensure better utilization and operation of the reactor in future
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2007.05.013Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2007.05.013;
- PII
- S0306-4549(07)00136-3;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 35
- Journal Issue
- 1
- Journal Page Range
- p. 141-147
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 39067551
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- AERE; BURNUP; CRITICALITY; FUEL ELEMENTS; FUEL MANAGEMENT; NEUTRON FLUX; NUCLEAR FUELS; REACTOR OPERATION; RESEARCH REACTORS; TRIGA TYPE REACTORS
- Descriptors DEC
- ENERGY SOURCES; ENRICHED URANIUM REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; MANAGEMENT; MATERIALS; NATIONAL ORGANIZATIONS; NUCLEAR MATERIALS MANAGEMENT; OPERATION; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SOLID HOMOGENEOUS REACTORS; UKAEA; UNITED KINGDOM ORGANIZATIONS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2007 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.