Calculation of kinetic parameters in an accelerator driven subcritical TRIGA reactor using MCNIC method
Creators
- 1. Nuclear Science and Technology Research Institute, AEOI, Tehran (Iran, Islamic Republic of)
- 2. Department of Radiation Application, Shahid Beheshti University, G.C, Tehran (Iran, Islamic Republic of)
Description
Highlights: • We proposed a methodology to calculate importance weighted kinetic parameters. • Kinetic parameters of the TRIGA reactor have been calculated using MCNIC method. • The results of the method have been validated. • Parameter Λ is highly sensitive to the reactor geometry and reflector thickness. • MCNIC method can efficiently be used to calculate the kinetic parameters in ADSRs. - Abstract: The effective delayed neutron fraction (βeff) and neutron reproduction time (Λ) play an important role in nuclear reactor control and safety analysis. In this work, calculation of these parameters in an Accelerator Driven Subcritical TRIGA reactor is investigated using MCNIC method. The result of this method has been compared with those obtained by MCNPX code, 1/v poisoning method and reference data. The relative difference between MCNIC method results with MCNPX code and reference data for βeff is −3.0% and 1.7%, respectively. Our results indicate that, the Λ value from MCNIC method has relative differences of −19.4% and −10.3% with MCNPX code and 1/v poisoning method calculations, respectively. These values are increased by increasing the reflector thickness. Finally, this method may be used for better estimation of kinetic parameters rather than the MCNPX code because of using neutron importance function
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2013.03.044Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2013.03.044;
- PII
- S0306-4549(13)00182-5;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 59
- Journal Page Range
- p. 188-193
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45112359
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR DRIVEN TRANSMUTATION; DELAYED NEUTRON FRACTION; MONTE CARLO METHOD; NEUTRON IMPORTANCE FUNCTION; NEUTRON REFLECTORS; NEUTRONS; REACTOR CONTROL SYSTEMS; REACTOR KINETICS; REACTOR SAFETY; SAFETY ANALYSIS; THICKNESS; TRIGA TYPE REACTORS
- Descriptors DEC
- BARYONS; CALCULATION METHODS; CONTROL SYSTEMS; DIMENSIONS; ELEMENTARY PARTICLES; ENRICHED URANIUM REACTORS; FERMIONS; FUNCTIONS; HADRONS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; KINETICS; NUCLEONS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; TRANSMUTATION; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2013 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.