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http://dx.doi.org/10.12989/eri.2015.3.2.125

Prompt neutron lifetime calculations for the NIRR-1 reactor  

Ibrahim, Yakubu V. (Centre for Energy Research and Training, Ahmadu Bello University)
Adeleye, Micheal O. (Bingham University)
Njinga, Raymond L. (Ibrahim Badamasi Babangida University)
Odoi, Henry C. (School of Nuclear and Allied Sciences, University of Ghana)
Jonah, Sunday A. (Centre for Energy Research and Training, Ahmadu Bello University)
Publication Information
Advances in Energy Research / v.3, no.2, 2015 , pp. 125-131 More about this Journal
Abstract
Prompt neutron lifetime calculations have been performed for the NIRR-1 reactor HEU and LEU cores using the 1/v insertion and the Adjoint flux weighing methods. Results of calculations obtained for the HEU and LEU cores are respectively $57.3{\pm}0.8$ and $47.5{\pm}0.7$ for the 1/v insertion and $56.9{\pm}0.3$ and $46.3{\pm}0.5$ for the Adjoint flux. There is a good agreement seen between the two methods for both cores. The prompt neutron lifetime was observed to be shorter in the LEU than for the HEU as expected. However, the Adjoint flux weighing method seemed to be the easiest method in calculating the prompt neutron lifetime for NIRR-1.
Keywords
prompt neutron lifetime; HEU; LEU; MCNP; enrichment; MNSR; neutron activation analysis;
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1 Abrefah, R.G., Odoi, H.C., Ampomah-Amoako, E. and Mensimah, E. (2012), "Investigation into the effects of Zircaloy-4 on the neutronics of low enriched uranium MNSR core", Prog. Nucl. Energy, 54(1), 5-10.   DOI   ScienceOn
2 Abtin, F., Feghhi, S.A.H. and Jafarikia, S. (2013), "Neutronic evaluations for MNSR research reactor core conversion from HEU to LEU", Ann. Nucl. Energy, 51, 69-73.   DOI   ScienceOn
3 Albert, L.H. and Diamond, D.J. (2006), "Calculation of the prompt neutron lifetime in NBSR", Nucl. Sci. Eng., 153, 26-32.   DOI
4 Bretscher, M.M. (1997), "Perterbation-Independent Methods for Calculating Research Reactor Kinetic Parameters", ANL/RERTR/TM-30, Argonne national Laboratory, December.
5 Final Safety Analysis Report of Nigeria Research Reactor-1, (2005), CERT Technical Report-CERT/NIRR-1/FSAR-01.
6 Haddad, K. and Boush, M. (2011), "Validation of MCNP volume efficiency calculation for gamma spectrometric assay of large NORM samples", J. Radio. Nucl. Chem., 289, 97-101.   DOI
7 Hamidatou, L. and Benkharfia, H. (2011), "Experimental and MCNP calculations of neutron flux parameters in irradiation channel at Es-Salam reactor", J. Radio. Nucl. Chem., 287, 971-975.   DOI
8 Heba, K.L. (2014), "Evaluation of effective prompt neutron lifetime for pressurized water reactors", Nucl. Tech., 188, 1-7.   DOI
9 Kiedrowski, B., Brown, F. and Wilson, P. (2011), "Adjoint-weighted tallies for k-eigenvalue calculations with continuous-energy Monte Carlo", Nucl. Sci. Eng., 168, 226-241.   DOI
10 Odoi, H.C., Akaho, E.H.K., Jonah, S.A., Abrefah, R.G. and Ibrahim, V.Y. (2014), "Study of criticality safety and neutronic performance for a 348-Fuel-Pin Ghana research reactor-1 LEU core using MCNP code", World J. Nucl. Sci. Tech., 4, 46-52.   DOI
11 Ibrahim, Y.V., Odoi, H.C., Njinga, R.L., Odeleye, M.O. and Jonah, S.A. (2012), "Monte Carlo simulation of additional safety control rod for commercial MNSR to enhance safety", Ann. Nucl. Energy, 44, 71-75.   DOI   ScienceOn
12 Ibrahim, Y.V., Odoi, H.C., Thomas, J.W. and Jonah, S.A. (2013), "Design options of control rod for low enriched uranium fueled NIRR-1 using Monte Carlo N-particle code", J. Nucl. Energy Sci. Power Gen. Tech., 2, doi:10.4172/2325-9809.1000104.   DOI
13 Jonah, S.A., Liaw, J.R. and Matos, J.E. (2007), "Monte Carlo simulation of core physics parameters of nigerian research reactor-1", Ann. Nucl. Energy, 34, 953-957.   DOI   ScienceOn
14 Jonah, S.A., Ibikunle, K. and Li, Y. (2009), "A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP", Ann. Nucl. Energy, 36, 1285-1286.   DOI   ScienceOn
15 Jonah, S.A., Ibrahim, Y.V., Ajujia, A.S. and Onimisi, M.Y. (2012), "The impact of HEU to LEU conversion of commercial MNSR: determination of neutron spectrum parameters in irradiation channels of NIRR-1 using MCNP code", Ann. Nucl. Energy, 39, 15-17.   DOI   ScienceOn
16 Khattab, K. and Sulieman, I. (2009), "Calculations of the thermal and fast neutron fluxes in the Syrian MNSR irradiation sites using the MCNP-4C code", Appl. Radiat. Isotop., 67, 535-538.   DOI   ScienceOn
17 Li, Y., Ke, G., Sun, Z., Shen, F., Liu, T. and Zhou, Y. (2009), "The study of physics and thermal characteristics for in-hospital neutron irradiator (INHI)", Appl. Radiat. Isotop., 67, S234-S237.   DOI   ScienceOn
18 Rabira, M.H. and Haha, C.J. (2013), "Evaluation of Delayed Neutron Fraction of RTP using MCNP", Transactions of the Korean Nuclear Society Spring Meeting, Gwangju, Korea, May.
19 MCNP5 (2003), A general Monte Carlo N-Particle Code, LA-UR-03-1987, Updates to the MCNP5 used for the delayed neutron fraction and prompt neutron lifetime calculations, Eds. B.C. Kiedrowski, T.E. Booth, F.B. Brown, J.S. Bull, J.A. Favorite, R.A. Forster, R.L. Martz, MCNP5-1.60 Feature Enhancements & Manual Clarifications, LA-UR-10-06217.
20 Peters, N.J., Brockman, J.D. and Robertson, J.D. (2009), "Using Monte Carlo transport to accurately predict isotope production and activation analysis rates at the University of Missouri research reactor", J. Radio. Nucl. Chem., 282, 255-259.   DOI
21 Shaaban, I. (2010), "Design of the thermal neutron beam for neutron radiography at the Syrian MNSR", Ann. Nucl. Energy, 37, 1588-1594.   DOI   ScienceOn
22 Snoj, L., Kavcic, A., Zerovnik, G. and Ravnik, M. (2010), "Calculation of kinetic parameters for mixed TRIGA cores with Monte Carlo", Ann. Nucl. Energy, 37, 223-229.   DOI   ScienceOn
23 Travelli, F.A. (1999), Progress of RERTR Programme, 22nd RERTR Meeting Budapest, Hungary.
24 Verboomen, B., Haec, W. and Baeten, P. (2006), "Monte Carlo calculation of the effective neutron generation time", Annal. Nucl. Energy, 33, 911-916.   DOI   ScienceOn