Determination of Epithermal Neutron Fluxes in the Cadmium-Lined Irradiation Channels of a Nuclear Reactor for Mineral Exploration

Authors

Keywords:

Reactor, Neutron flux, Highly-enriched Uranium, Low-enriched Uranium, Epithermal

Abstract

mineral deposits in soil or rock samples using method such as neutron activation analysis (NAA). Neutron flux is an important requirement for this method. Epithermal neutrons induced nuclear reactions more efficiently than with thermal neutrons when analyzing elements with high resonance integrals, it is also useful in analyzing element such as Uranium, Thorium and certain transition metals. In this study, epithermal neutron fluxes in channels of Nigeria Research Reactor-1 (NIRR-1) installed with Cadmium (Cd) were determined for use in NAA procedures. The measurements were performed after Low Enriched Uranium (LEU) fuel substituted the High enriched Uranium (HEU) fuel in the reactor. The epithermal neutron fluxes were experimentally determined using Al-0.1%Au monitor foil via 197Au(n,γ)198Au reaction. The epithermal neutron fluxes determined in the inner and outer Cd-lined irradiation channels A1 and A2 were found to be 2.539×1010 n/cm2s and 4.459×109 n/cm2s respectively at half operating power (15 kW) which corresponds to a thermal neutron flux of 5×1011 n/cm2s on the control console of NIRR-1. The values obtained before fuel conversion by previous authors in the A1-inner irradiation channel and in the A2-Outer Cd-lined irradiation channel were 2.72×1010 n/cm2s and 4.459×109 n/cm2s respectively. These values were both in agreement with the values of this study. This shows that the Cd installation and the fuel conversion from the (HEU LEU does not affect the epithermal neutron fluxes. It also implies that the stability of the neutrons in NIRR-1 were not altered. Thus, the facility is good for Epithermal NAA. The use of additional flux monitors, implementation of ENAA in geochemical analysis and evaluation of epithermal neutron shaping factor (α) were recommended.

Dimensions

Akar Tarim U., Gurler O., (2018). Source-to-detector Distance Dependence of Efficiency and Energy Resolution of a 3"x3" NaI(Tl) Detector. Avrupa Bilim ve Teknoloji Dergisi 13; 103-107.

Anas, M. S., Jonah, S. A., Rabiu N., N. N. Garba., T. Muhammad., (2023). Development of Neutron Activation Analysis (NAA) Protocols for NIRR-1 irradiation and counting facilities after conversion to low enriched uranium (LEU) core,Sci set J of Physics 2(1).01-06.

Faanu A., Emi-Reynolds G., Darko E.O., Awudu R., Glover E.T., Adukpo O.K., Otoo F.,Kpeglo D.O., Lawluvi H. (2011). Calibration and Performance Testing of Sodium Iodide, NaI(Tl), Detector at the Food and Environmental Laboratory of the Radiation Protection Institute of the Ghana Atomic Energy Commission. West African Journal of Applied Ecology, 19(1), 39-52.

Greenberg, R. R., Bode, P., & Fernandes, E.A.D.N. (2011). Neutron activation analysis: a primary method of measurement. Spectrochimica Acta Part B: Atomic Spectroscopy, 66(3-4), 193-241.

IAEA (2023). ‘Neutron activation analysis’, Available at: https://www.iaea.org/topics/neutron-activation-analysis (Accessed: 29 November, 2023).

Jonah, S., Balogun, G., Umar, I., & Mayaki, M. (2005). Neutron spectrum parameters in irradiation channels of the Nigeria Research Reactor-1 (NIRR-1) for the k 0-NAA standardization. Journal of Radioanalytical and Nuclear Chemistry, 266(1), 83-88.

Jonah, S. A. Umar, I. M., Oladipo, M. O. A., Balogun, G. I. & Adeyemo, D.J. (2006). Standardization of NIRR-1 irradiation and counting facilities for instrumental neutron activation analysis. Applied Radiation and Isotopes, 64, pp. 818-822.

Jonah SA, Ibrahim YV, Akaho EHK (2008). The determination of reactor spectrum-averaged cross-sections in miniature neutron source reactor facility. 66: 1377- 80.http://dx.doi.org/10.10162008.04.001

Jonah S.A., Ibikunle k., Li y (2009), A feasibility study of LEU enrichment uranium fuels for MNSR conversion using MCNP” Annals of Nuclear Energy 36 1285–1286.

Musa, Y., Ahmed, Y., Yamusa, Y., & Ewa, I. (2012). Determination of radial and axial neutron flux distribution in irradiation channel of NIRR-1 using foil activation technique. Annals of nuclear energy, 50, 50-55.

Njinga, R.L., Ewa, I.O.B., Jonah, S.A., Baba, A., Ahmed, Y.A., Agbo, G.A., Ebobenow, J. and Nasiru, R. (2012) Alternative Approach for Efficiency Data Generation in Neutron Activation Analysis. International Journal of Applied Science and Technology, 1, 244-256.

R. B. M. Sogbadji, et al., Nuclear Engineering and Design, Vol. 240, 2010, pp. 980-984. http://dx.doi.org/10.1016/j.nucengdes.2009.12.020

Son and Tan SpringerPlus (2016) 5:863 http://dx.doi.org/10.1186/s40064-016-2585-7

Sadiq, U., Jonah, S.A., Nasiru, R. and Zakari, Y.I. (2005), Neutron Spectrum Parameters in Two Irradiation Channels of the Nigerian Research Reactor-1(NIRR-1) for usein ko-NAA, Bayero Journal of Pure and Applied Sciences, 3(1): 220-223.

Sadiq, U., Jonah, S.A., Nasiru, R. and Zakari, Y.I. (2010), Neutron Spectrum Parametersin Two Irradiation Channels of the Nigerian Research Reactor-1(NIRR-1) for usein ko-NAA, Bayero Journal of Pure and Applied Sciences, 3(1): 220-223.

Sheyin, F., Oladipo, M., Jonah, S., & Sadiq, U. (2015). Determination of α in the Cadmium Lined Irradiation Channel of the NIRR-1 for Use in k o-ENAA. World Journal of Nuclear Science and Technology, 5(03), 233.

Published

2025-09-14

How to Cite

Determination of Epithermal Neutron Fluxes in the Cadmium-Lined Irradiation Channels of a Nuclear Reactor for Mineral Exploration. (2025). Nigerian Journal of Applied Physics, 1(1), 48-56. https://doi.org/10.62292/njap-v1i1-2025-20

How to Cite

Determination of Epithermal Neutron Fluxes in the Cadmium-Lined Irradiation Channels of a Nuclear Reactor for Mineral Exploration. (2025). Nigerian Journal of Applied Physics, 1(1), 48-56. https://doi.org/10.62292/njap-v1i1-2025-20