Effects of Pu and MA uniform and nonuniform distributions on subcritical multiplication of TRIGA Mark II ADS reactor
- 1. Physics Department, College of Sciences and Humanities, Prince Sattam Bin Abdulaziz University, Kharj (Saudi Arabia)
- 2. Physics Department, Faculty of Science, Ain Shams University, Cairo (Egypt)
- 3. Physics Department, Faculty of Science, Amran University, Amran (Yemen)
- 4. Nuclear and Radiation Regulatory Authority (NRRA), Cairo (Egypt)
Description
Highlights: • The effects of distributions of Pu/MA samples in TRIGA Mark II ADS core were numerically investigated. • The neutron flux and spectrum of the two distributions were studied. • Plutonium and minor actinides fission rate were slightly higher in nonuniform distribution than that in uniform distribution. • The maximum total fission rate in the core was achieved with Pu/MA uniform distribution. • Neutron multiplication and source efficiency increased in the case of Pu/MA uniform distribution. - Abstract: Plutonium (Pu) and minor actinides (MAs) are responsible for the majority of radiotoxicity, heat generation, and proliferation risk of nuclear spent fuel. Accelerator driven system (ADS) reactors can employ Pu and MA for transmutation and power generation within improved safety scheme. Pu and MA can be loaded in ADS reactor core in a variety of distributions. In this study, the effects of uniform and nonuniform distributions of Pu and MA samples loaded within enriched uranium fuel elements inside UT-TRIGA Mark II ADS reactor on neutron flux, neutron spectrum, fission rate, and subcritical multiplication parameters were numerically investigated using Monte Carlo MCNPX transport code. The type of distribution producing higher subcritical multiplication and source efficiency will contribute in minimizing the accelerator current requirements for ADS operation.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.anucene.2016.03.016Additional details
Identifiers
- DOI
- 10.1016/j.anucene.2016.03.016;
- PII
- S0306-4549(16)30139-6;
Publishing Information
- Journal Title
- Annals of Nuclear Energy (Oxford)
- Journal Volume
- 94
- Journal Page Range
- p. 332-337
- ISSN
- 0306-4549
- CODEN
- ANENDJ
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 47125266
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- ACCELERATOR-DRIVEN SUBCRITICAL SYSTEMS; ENRICHED URANIUM; FISSION; FUEL ELEMENTS; M CODES; MONTE CARLO METHOD; MULTIPLICATION FACTORS; NEUTRON FLUX; NEUTRON SPECTRA; PLUTONIUM; POWER GENERATION; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; SPENT FUELS; TRANSMUTATION; TRIGA TYPE REACTORS
- Descriptors DEC
- ACTINIDES; CALCULATION METHODS; COMPUTER CODES; DIMENSIONLESS NUMBERS; ELEMENTS; ENERGY SOURCES; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; FUELS; HOMOGENEOUS REACTORS; HYDRIDE MODERATED REACTORS; ISOTOPE ENRICHED MATERIALS; MATERIALS; METALS; NUCLEAR FUELS; NUCLEAR REACTIONS; OPERATION; RADIATION FLUX; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SAFETY; SOLID HOMOGENEOUS REACTORS; SPECTRA; SUBCRITICAL ASSEMBLIES; TRANSURANIUM ELEMENTS; URANIUM; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Copyright
- Copyright (c) 2016 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.