Research ArticleOpen AccessGoogle Scholar indexed
Prediction of Neutronic and Kinetic Parameters of Ghana Research Reactor 1 (GHARR-1) after 19 Years of Operation Using Monte Carlo-N Particle (MCNP) Code
National Institute for Scientific and Industrial Research, Lusaka, Zambia
School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
- 1 National Institute for Scientific and Industrial Research, Lusaka, Zambia
- 2 School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
- 3 School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
- 4 School of Nuclear and Allied Sciences, University of Ghana, Accra, Ghana
World Journal of Nuclear Science and Technology·Volume 08 (2018)·Pages 160–175·Published 26 September 2018·DOI10.4236/wjnst.2018.84014
Copy link · social · email
Abstract
The Ghana Research Reactor-1 (GHARR-1) core was modified with an addition of a 9.0 mm layer of beryllium to the top shim tray to compensate for reactivity loss due to fuel depletion after 19 years of operation. Neutronic and kinetic parameters have been predicted using Monte Carlo N-Particle Code version 5 (MCNP5) to determine whether they were within acceptable operating margins. Excess reactivity, control rod worth, moderator reactivity coefficient, delayed neutron fraction and neutron generation time have been predicted as 3.86, 6.98, − 0.1218 mk/ ° C, 8.17507 × 10 − 3 Δ k/k, and 8.147 × 10 − 5 s respectively. These parameters compared favorably with those provided in the initial Safety Analysis Report.
KeywordsDelayed Neutron FractionNeutron Generation TimeModerator Reactivity CoefficientPower Peaking Factor
- Physics Section International Atomic Energy Agency (1980) Research Reactor Core Conversion from the Use of Highly Enriched Uranium to the Use of Low Enriched Uranium Fuels. IAEA-TECDOC-233, Vienna.
- Mweetwa, B.M., Ampomah-Amoako, E. and Akaho, E.H.K. (2015) Evaluation of Safety Parameters for Ghana Research Reactor-1 after Nineteen (19) Years of Operation Using REBUS/ANL, MCNP5, PARET/ANL and PLTEMP/ANL Simulation Codes. University of Ghana, Accra.
- Odoi, H.C., Akaho, E.H.K., Nyarko, B.J.B., Abrefah, R.G., Ampomah-Amoako, E., Sogbadji, R.B.M. and Birikorang, S.A. (2012) Conversion of International MNSR—Reference Case of Ghana MNSR. RERTR 2012, 34th International Meeting on Reduced Enrichment for Research and Test Reactors, Warsaw, 14-17 October 2012, S12-P2.
- Akaho, E.H.K., Anim-Sampong, S., Dodoo-Amoo, D.N.A., Maakuu, B.T., Emi Reynolds, G., Osae, E.K., Boadu, H.O. and Bamford, S.A. (2003) Ghana Research Reactor-1 Final Safety Analysis Report. Ghana Atomic Energy Technical Report. GAEC-NNRI, RT-90, GEAC, Accra.
- Adoo, N.A., Nyarko, B.J.B., Akaho, E.H.K., Alhassan, E., Agbodemegbe, V.Y., Bansah, C.Y. and Della, R. (2011) Determination of Thermal Hydraulic Data of GHARR-1 under Reactivity Insertion Transients Using the PARET/ANL Code. Nuclear Engineering and Design, 241, 5203-5210.
- Cardoni, J.N. (2011) Nuclear Reactor Multi-Physics Simulations with Coupled MCNP5 and STAR-CCM+. International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2011), Rio de Janeiro, May 8-12, 2011, 3.
- http://www.nuclear-power.net/nuclear-power/reactor-physics/reactor-dynamics/reactor-kinetics/
- Khan, M.J.H. and Islam, S.M.A. (2013) Analysis of Kinetic Parameters of 3 MW TRIGA MARK-II Research Reactor Using SRAC 2006 Code System. Annals of Nuclear Energy, 60, 181-186.
- Farshad, F., Khalafi H. and Mirvakili, S.M. (2011) A Literature Survey of Neutronics and Thermal-Hydraulics Codes for Investigating Reactor Core Parameters; Artificial Neural Networks as the VVER-1000 Core Predictor. Nuclear Power Pavel Tsvetkov, IntechOpen. https://doi.org/10.5772/16521
- Broeders, C.H.M. (2000) A Comparison of Some Neutronics Characteristics of Critical Reactors and Accelerator Driven Subcritical Systems. Forschungszentrum Karlsruhe, Karlsruhe, Germany.
- http://www.nuclear-power.net/nuclear-power/fission/prompt-neutrons/prompt- generation-time-mean-generation-time/