THE NIGERIAN RESEARCH REACTOR-1 (NIRR-1) POWER AND ISOTHERMAL TEMPERATURE PARAMETERS MEASUREMENTS

  • S. M. Hussaini
  • Mary T. Ekwu
  • M. Ndawashi
Keywords: NIRR-1, Isothermal temperature, Miniature neutron source reactor, power levels

References

Agbo, S.A., Ahmed, Y.A., Yahaya, J., & Ewa, I.O.B., (2016). Analysis of Nigeria research reactor-1 (NIRR 1) thermal power calibration methods. Nuclear Engineering and Techn., 48: 673-683. DOI: https://doi.org/10.1016/j.net.2016.01.014

Ahmed, Y.A., Balogun, G.I., Jonah, S.A., Funtua I.I. (2008): the behavior of reactor power and flux resulting from changes in core-coolant temperature for a miniature neutron source reactor, Annals of Nuclear Energy, 35:2417-2419. DOI: https://doi.org/10.1016/j.anucene.2008.08.005

Ahmed, Y.A., Mansir, I.B., Yusuf, I., Balogun, G.I., and Jonah, S.A. (2011). Effects of Core Excess reactivity and coolant average temperature on maximum operable time of NIRR-1 MNSR. Nuclear engineering and design 241, 1569-1564 DOI: https://doi.org/10.1016/j.nucengdes.2011.01.038

Ahmed, Y.A., Ewa I.O.B., Umar, I.M., Bezboruah, T., Johri, M. & Akaho ,E.H.K. (2006). The low power miniature neutron source reactors: Design, safety and applications; UNESCO/IAEA/ICTP Publication IC/2006/020. The Abdus Salam International Centre for Theoretical Physics, Trieste, Italy. http://www.ictp.it/pub_off.

Bullock, J.B. (1965). Absolute power measurements of the ford nuclear reactor, paper presented at the ANS conference on reactor operating experience Moran (Wy).

Mesquita, A.Z., Rezende, H.C., & Tambourgi, E.B., (2007). Power calibration of the TRIGA Mark II nuclear research reactor. J. Brazilian Soc. Mechan. Sci. and Engr., XXIX(3): 240-245. DOI: https://doi.org/10.1590/S1678-58782007000300002

Musa, Y., Ahmed, Y.A., Yamusa, Y.A., Ewa, I.O.B (2012). Determination of radial and axial flux distribution in a irradiation channels of NIRR-1 using foil activation technique. Annals of Nuclear engineering 50:50-55. DOI: https://doi.org/10.1016/j.anucene.2012.07.014

Qazi, M.K., Akaho, E.H.K., Maakuu, B.T. and Anim-Sampong, S. (1996). Nuclear core design Analysis of Ghana research reactor -1.NNR-1 technical report.

Salawu, A. and Balogun, G.I. (2007). Prediction of peak temperature of NIRR-1 core components under several reactivity accident tests. FUOYE journal of engineering and technology, 2(1). DOI: https://doi.org/10.46792/fuoyejet.v2i1.59

Yahaya, B., Ahmed, Y.A., Balogun G.I., and Agbo, S.A. (2017). Estimating NIRR-1 burn-up and core life time expectancy using the codes WIMS and Citations. Results in Physics, 7, 596-603. DOI: https://doi.org/10.1016/j.rinp.2017.01.017

Yang, Y. (1992). Reactor complex manual. CIAE Technical report code MNSR DC-3

Published
2023-08-30
How to Cite
Hussaini S. M., Ekwu M. T., & Ndawashi M. (2023). THE NIGERIAN RESEARCH REACTOR-1 (NIRR-1) POWER AND ISOTHERMAL TEMPERATURE PARAMETERS MEASUREMENTS. FUDMA JOURNAL OF SCIENCES, 7(4), 171 - 174. https://doi.org/10.33003/fjs-2023-0704-1913