Sensitivity analysis of core neutronic parameters in accelerator driven subcritical reactors
Creators
- 1. Nuclear Science and Technology Research Institute, AEOI, Tehran (Iran, Islamic Republic of)
- 2. Radiation Application Department, Shahid Beheshti University, G.C, Tehran (Iran, Islamic Republic of)
Description
Highlights: • Sensitivity analysis of ADSR core neutronic parameters has been investigated. • Uniform and parabolic proton beam spatial distributions have been considered. • TRIGA reactor was considered as the case study of the problem. - Abstract: In this paper, sensitivity of the ADSRs core neutronic parameters to the accelerator related parameters such as beam profile, source multiplication coefficient (ks) and proton beam energy (Ep) has been investigated. TRIGA reactor has been considered as the case study of the problem. Monte Carlo code MCNPX has been used to calculate neutronic parameters such as: effective multiplication coefficient (keff), net neutron multiplication (M), spallation neutron yield (Yn/p), energy constant gain (G0), energy gain (G), importance of neutron source (φ*), axial and radial distributions of neutron flux and power peaking factor (Pmax/Pave) in two axial and radial directions of the reactor core for three eigen values levels (ks) including: 0.91, 0.97 and 0.99. According to the results, using a parabolic spatial distribution instead of a uniform spatial distribution increases the relative differences of spallation neutron yield, net neutron multiplication and energy gain by 4.74%, 4.05% and 10.26% respectively. In consequence the required accelerator current (Ip) will be reduced by 7.14% to preserve the reactivity. Although safety margin is decreased in highest case of ks, but energy gain increases by 93.43% and the required accelerator current and importance of neutrons source decrease by 48.3% and 2.64% respectively. In addition, increasing Ep from 115 MeV up to1 GeV, improves spallation neutron yield and energy gain by 2798.71% and 205.12% and decreases the required accelerator current and power by 96.83% and 72.44%, respectively. Therefore, our results are indicative of the fact that investigating sensitivity of the core neutronic parameters to the accelerator related parameters are necessary in order to optimally design a cost-efficient ADSR
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2013.07.046Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2013.07.046;
- PII
- S0306-4549(13)00401-5;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 63
- Journal Page Range
- p. 228-232
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 45112394
- Subject category
- S43: PARTICLE ACCELERATORS;
- Descriptors DEI
- ACCELERATOR DRIVEN TRANSMUTATION; BEAM CURRENTS; BEAM PROFILES; GEV RANGE; MEV RANGE; MONTE CARLO METHOD; NEUTRON FLUX; NEUTRON SOURCES; NEUTRONS; PROTON BEAMS; REACTOR CORES; SAFETY MARGINS; SENSITIVITY ANALYSIS; SPALLATION; SPATIAL DISTRIBUTION; TRIGA TYPE REACTORS
- Descriptors DEC
- BARYONS; BEAMS; CALCULATION METHODS; CURRENTS; DISTRIBUTION; ELEMENTARY PARTICLES; ENERGY RANGE; ENRICHED URANIUM REACTORS; FERMIONS; HADRONS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; NUCLEAR REACTIONS; NUCLEON BEAMS; NUCLEONS; PARTICLE BEAMS; PARTICLE SOURCES; RADIATION FLUX; RADIATION SOURCES; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; 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.