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http://dx.doi.org/10.1016/j.net.2016.01.014

Analysis of Nigeria Research Reactor-1 Thermal Power Calibration Methods  

Agbo, Sunday Arome (Physics Department, Ahmadu Bello University)
Ahmed, Yusuf Aminu (Centre for Energy Research and Training, Ahmadu Bello University)
Ewa, Ita Okon Bassey (Centre for Energy Research and Training, Ahmadu Bello University)
Jibrin, Yahaya (Physics Department, Ahmadu Bello University)
Publication Information
Nuclear Engineering and Technology / v.48, no.3, 2016 , pp. 673-683 More about this Journal
Abstract
This paper analyzes the accuracy of the methods used in calibrating the thermal power of Nigeria Research Reactor-1 (NIRR-1), a low-power miniature neutron source reactor located at the Centre for Energy Research and Training, Ahmadu Bello University, Zaria, Nigeria. The calibration was performed at three different power levels: low power (3.6 kW), half power (15 kW), and full power (30 kW). Two methods were used in the calibration, namely, slope and heat balance methods. The thermal power obtained by the heat balance method at low power, half power, and full power was $3.7{\pm}0.2kW$, $15.2{\pm}1.2kW$, and $30.7{\pm}2.5kW$, respectively. The thermal power obtained by the slope method at half power and full power was $15.8{\pm}0.7kW$ and $30.2{\pm}1.5kW$, respectively. It was observed that the slope method is more accurate with deviations of 4% and 5% for calibrations at half and full power, respectively, although the linear fit (slope method) on average temperature-rising rates during the thermal power calibration procedure at low power (3.6 kW) is not fitting. As such, the slope method of power calibration is not suitable at lower power for NIRR-1.
Keywords
Heat Balance; Miniature Neutron Source Reactor; Nuclear Research Reactor; Slope; Temperature; Thermal Hydraulic;
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  • Reference
1 M. Podvratnik, Calculations to support absolute thermal power calibration of the Slovenian TRIGA Mark II reactor, 20th International Conference "Nuclear Energy for New Europe," Bovec (Slovenia), September 12-15, 2011.
2 Y. Musa, Y.A. Ahmed, Y.A. Yamusa, I.O.B. Ewa, Determination of radial and axial flux distribution in irradiation channels of NIRR-1 using foil activation technique, Ann. Nucl. Energy 50 (2012) 50-55.   DOI
3 R.M.G.P. Souza, A.Z. Mesquita, M.F.R. Resende, E.S. Valente, Resultados dos Testes Finais para o Aumento de Potencia do Reator TRIGA IPR-R1 (CDTN/CNEN NI-IT4-07/02), Belo Horizonte (Brazil), 2002.
4 J. Shaw, Reactor Operation, Pergamon Press, Oxford (UK), 1969.
5 S.A. Agbo, Y.A. Ahmed, B. Yayaha, U. Iliyasu, The use of heat balance method in the thermal power calibration of Nigeria Research Reactor-1 (NIIR-1), Prog. Nucl. Energy 85 (2015) 344-351.   DOI
6 A.Z. Mesquita, H.C. Rezende, R.M.G.P. Souza, Thermal power calibrations of the IPR-R1 TRIGA reactor by the calorimetric and the heat balance methods, Prog. Nucl. Energy 53 (2011) 1197-1203.   DOI
7 A.Z. Mesquita, H.C. Rezende, E.B. Tambourgi, Power calibration of the TRIGA Mark I nuclear research reactor, J. Braz. Soc. Mech. Sci. Eng. XXIX (2007) 240-245.
8 J.B. Bullock, Absolute power measurements of the Ford nuclear reactor, Paper Presented at the ANS Conference on Reactor Operating Experience, Moran (WY), July 28-30, 1965.
9 T. Zagar, M. Ravnik, A. Persic, Analysis of reactor thermal power calibration method, Proceedings of the International Conference Nuclear Energy in Central Europe, Portoroz (Slovenia), September 6-9, 1999, pp. 91-98.
10 S.A. Jonah, Y.V. Ibrahim, M. Kalimulla, J.E. Matos, Steady state thermal hydraulic operational parameters and safety margins of NIRR-1 with LEU fuel using PLTEMP-ANL code, European Nuclear Conference (ENC), Manchester (UK), December 9-12, 2012.
11 Z. Yongmao, Technology and Use of low power research reactors, Report of IAEA Consultants Meeting (Report No. IAEA-TECDOC-384), Beijing (China), April 30-May 3, 1985, p. 8998.
12 G.I. Balogun, S.A. Jonah, I.M. Umar, Measures aimed at enhancing safe operation of the Nigeria Research Reactor-1 (NIRR-1), in: Book of Contributed Papers, International Conference on Operational Safety Performance in Nuclear Installations (IAEA-CN-133/19), IAEA, Vienna (Austria), November 30-December 2, 2005, pp. 93-96.
13 Y.A. Ahmed, I.B. Mansir, I. Yusuf, G.I. Balogun, S.A. Jonah, Effects of core excess reactivity and coolant average temperature on maximum operable time of NIRR-1 miniature neutron source reactor, Nucl. Eng. Des. 241 (2011) 1559-1564.   DOI
14 S.A. Jonah, G.I. Balogun, I.M. Umar, M.C. Mayaki, Neutron spectrum parameters in irradiation channels of the Nigeria Research Reactor-1 (NIRR-1) for the k0-NAA standardization, J. Radioanal. Nucl. Chem. 266 (2005) 83-88.   DOI
15 S.A. Jonah, I.M. Umar, M.O.A. Oladipo, G.I. Balogun, D.J. Adeyemo, Standardization of NIRR-1 irradiation and counting facilities for instrumental neutron activation analysis, Appl. Radiat. Isot. 64 (2006) 818-822.   DOI
16 Y.A. Ahmed, G.I. Balogun, S.A. Jonah, I.I. Funtua, The behavior of reactor power and flux resulting from changes in core-coolant temperature for a miniature neutron source reactor, Ann. Nucl. Energy 35 (2008) 2417-2419.   DOI
17 Y.A. Ahmed, I.B. Mansir, B.B.M. Dewu, Installation of permanent cadmium-lined channel as a means for increasing epithermal NAA capabilities of miniature neutron source reactors, Nucl. Eng. Des. 263 (2013) 70-76.   DOI
18 Department of Energy (DoE), DOE-HDBK-1019/2-93, Department of Energy Fundamentals Handbook: Nuclear Physics and Reactor Theory (Neutron Characteristics), vol. 2, DoE, Washington D.C. (WA), 1993, p. 1-37.
19 I.B. Mansir, G.Y. Pam, C.O. Folayan, Effects of density variation on the cooling of the Nigeria Research Reactor-1 (NIRR-1), Adv. Appl. Sci. Res. 3 (2012) 110-116.
20 F.P. Incropera, D.P. DeWitt, T.L. Bergman, A.S. Lavine. Fundamentals of Heat and Mass Transfer, sixth ed., John Wiley and Sons, New Jersey, 2007, pp. 96-657.
21 Y. Cengel, M. Boles, Property tables and charts, in: Thermodynamics an Engineering Approach, fifth ed., McGraw Hill, Boston (MA), 2005, pp. 27-963.
22 J.P. Holman, Experimental Methods for Engineers, seventh ed., McGraw-Hill, Boston (MA), 1998.
23 J.P. Holman, Heat Transfer, ninth ed., McGraw-Hill, New York, 2002.
24 Centre for Energy Research and Training (CERT), Final Safety Analysis Report of Nigeria Research Reactor-1 (NIRR-1/SAR), CERT Technical Report No. CERT/NIRR-1/FSAR-01, CERT, Zaria (Nigeria), 2005.
25 R.S. Figliola, D.E. Beasley, Theory and Design for Mechanical Measurements, John Wiley & Sons, New York, 1991.