The nuclear technology has been widely used in the world. The research of measurement in nuclear installations involves many aspects, such as nuclear reactors, nuclear fuel cycle, safety and security, nuclear accident, after action, analysis, and environmental applications. In last decades, many advanced measuring devices and techniques have been widely applied in nuclear installations. This paper mainly introduces the development of the measuring (instrumentation) methods for nuclear installations and the applications of these instruments and methods. 1. Introduction In last decade, nuclear technology has developed rapidly and became more important to human society with the development of science and technology. Nuclear technology has many advantages, such as zero carbon emissions, energy independence, and safety. At present, nuclear installations are more prevalent than ever before. Therefore, with the rapid development and wide applications of nuclear technology, many new technologies have been emerging to guarantee its reliability and safety, where measuring devices and techniques that can exactly measure and monitor the nuclear installations show particular importance. This paper is a review of advances in measuring (instrumentation) technology focus areas that have applications in nuclear installations. The instruments used in nuclear installations mainly include multifarious detectors, sensors, and meters. The measurement methods for nuclear technology mostly consist of all kinds of nondestructive measurement methods. The paper presents various instruments and measurement methods which are widely used in nuclear power reactors, nuclear fuel cycle, safeguards and homeland security, nuclear accident, after action, and analysis. 2. Nuclear Power Reactors 2.1. Nuclear Power Reactors Instrumentations In this section, instrumentations to measuring the neutron fission, the neutron dose, the flux, the reactor fission rate, and temperature are discussed. Here instrumentations contain Micro-Me-gas detectors, noise thermometer, tissue equivalent proportional counter, high-temperature thermocouples, liquid scintillation detector, spectrometers, optical fiber sensors, Uranium Fission chamber, Plutonium Fission chamber, Self-Powered Neutron Detector, Ionization chamber, Self-Powered Gamma Detector, Differential calorimeter, Gamma Thermometer, and Optical Fiber Sensors, and so forth. A new set-up at the Conseil Europeen pour la Recherche Nucleaire (CERN) n_TOF facility has been built and tested by Guerrero et al. which allowed measuring simultaneously neutron,
References
[1]
C. Guerrero, E. Berthoumieux, D. Cano-Ott, F. Gunsing, E. Mendoza, and S. Andriamonje, “A new set-up for the simultaneous measurement of neutro-induced capture and fission reactions,” in Proceedings of the 2nd International Conference on Advancements in Nuclear Instrumentation Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[2]
I. Bolshakova, V. Chekanov, I. Duran et al., “Methods and instrumentation for investigating hall sensors during their irradiation in nuclear research reactors,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[3]
R. I. Scherpelz and J. E. Tanner, “Neutron measurements at nuclear power reactors [55],” Nuclear Instruments and Methods in Physics Research A, vol. 476, no. 1-2, pp. 400–404, 2002.
[4]
D. Fourmentel, J.-F. Villard, A. Lyoussi et al., “Combined analysis of neutron and photon flux measurements for the Jules Horowitz reactor core mapping,” in Proceedings of the 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[5]
H. G. Brixy, “Temperature measurement in nuclear reactors by noise thermometry,” Nuclear Instruments and Methods, vol. 97, no. 1, pp. 75–80, 1971.
[6]
T. Bily and L. Sklenka, “Neutronic design of instrumentation for thermal effects measurement on VR-1 reactor,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[7]
J. L. Rempe, D. L. Knudson, J. E. Daw et al., “Enhanced in-pile instrumentation at the advanced test reactor,” in Proceedings of the 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[8]
A. Porta, V. M. Bui, M. Cribier et al., “Reactor neutrino detection for non-proliferation with the NUCIFER experiment,” IEEE Transactions on Nuclear Science, vol. 57, no. 5, pp. 2732–2739, 2010.
[9]
J. F. Villard, S. Fourrez, D. Fourmentel, and A. Legrand, “Improving high-temperature measurements in nuclear reactors with Mo/Nb thermocouples,” International Journal of Thermophysics, vol. 29, no. 5, pp. 1848–1857, 2008.
[10]
G. Cheymol, B. Brichard, and J. F. Villard, “Fibre optics for metrology in nuclear research reactors applications to dimensional measurements,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[11]
G. Y. Buimistriuc and A. M. Rogov, “Intelligent fiber optic pressure sensor for measurements in extreme conditions,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[12]
C. Papastefanou, “Measurement of neutron flux and albedo of water for thermal neutrons with foils of indium in a subcritical nuclear reactor,” Journal of Radioanalytical and Nuclear Chemistry, vol. 261, no. 3, pp. 671–678, 2004.
[13]
Y. G. Li, Y. Q. Shi, Y. B. Zhang, and P. Xia, “Reactor fission rate measurement for miniature neutron source reactor by solid state nuclear track detector,” Radiation Measurements, vol. 34, no. 1–6, pp. 589–591, 2001.
[14]
M. Laurie, M. A. Fütterer, J. M. Lapetite, S. Fourrez, and R. MoriceNew, “new temperature monitoring devices for high-temperature irradiation experiments in the high flux reactor petten,” Nuclear Science, vol. 58, pp. 2319–2324, 2011.
[15]
N. Khentout and B. Meftah, “Design and realization of a measurement system of cold neutron speeds by TOF method,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[16]
A. K. Bhattacharya, J. T. Verdeyen, F. T. Adler, and L. Goldstein, “Measurement of the local radiation field in a nuclear reactor by microwave interferometric techniques,” Nuclear Instruments and Methods, vol. 95, no. 2, pp. 313–325, 1971.
[17]
O. Meirav, M. Adam, E. Boaretto et al., “Measurements of 129I in a nuclear power reactor by accelerator mass spectrometry,” International Journal of Radiation Applications and Instrumentation A, vol. 43, no. 11, pp. 1420–1424, 1992.
[18]
R. Coulon, S. Normand, G. Ban et al., “Sodium fast reactor power monitoring using 20F tagging agent,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[19]
A. K. Sang, M. E. Froggatt, D. K. Gifford, S. T. Kreger, and B. D. Dickerson, “One centimeter spatial resolution temperature measurements in a nuclear reactor using Rayleigh scatter in optical fiber,” IEEE Sensors Journal, vol. 8, no. 7, pp. 1375–1380, 2008.
[20]
L. K. Yarovoi, L. Y. Robur, A. V. Gnatovsky, and E. P. Vdalov, “holographic equipment for testing the construction of the nuclear power plant,” in Proceedings of the 4th Regional Meeting, 1997.
[21]
S. D. Eastham, D. J. Coates, and G. T. Parks, “A novel method for rapid comparative quantitative analysis of nuclear fuel cycles,” Annals of Nuclear Energy, vol. 42, pp. 80–88, 2012.
[22]
M. H. Noiré, L. Couston, E. Douarre, D. Pouyat, C. Bouzon, and P. Marty, “A new sol-gel derived optical fiber sensor for high acidity measurements: application in nuclear fuel reprocessing,” Journal of Sol-Gel Science and Technology, vol. 17, no. 2, pp. 131–136, 2000.
[23]
I. Matsson, B. Grapengiesser, and B. Andersson, “LOKET-a gamma-ray spectroscopy system for in-pool measurements of thermal power distribution in irradiated nuclear fuel,” Nuclear Instruments and Methods in Physics Research A, vol. 569, no. 3, pp. 872–882, 2006.
[24]
L. Viererbl, Z. Lahodová, A. Voljanskij et al., “Measurement of gamma and neutron radiations inside spent fuel assemblies with passive detectors,” Nuclear Instruments and Methods in Physics Research A, vol. 652, no. 1, pp. 90–93, 2011.
[25]
M. Battaglieri, R. de Vita, G. Firpo et al., “An anti-neutrino detector to monitor nuclear reactor's power and fuel composition,” Nuclear Instruments and Methods in Physics Research A, vol. 617, no. 1–3, pp. 209–213, 2010.
[26]
P. F. Peck, “Control analysis of 235U in nuclear fuel by a neutron absorption method,” Journal of Radioanalytical Chemistry, vol. 48, no. 1-2, pp. 73–82, 1979.
[27]
G. Perret and K. A. Jordan, “On the combination of delayed neutron and delayed gamma techniques for fission rate measurement in nuclear fuel,” in Proceedings of the 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[28]
X. Y. Liu, D. A. Andersson, and B. P. Uberuaga, “First-principles DFT modeling of nuclear fuel materials,” Journal of Materials Science, vol. 47, no. 21, pp. 7367–7384, 2012.
[29]
E. Rosenkrantz, J. Y. Ferrandis, G. Leveque, and D. Baron, “Ultrasonic measurement of gas pressure and composition for nuclear fuel rods,” Nuclear Instruments and Methods in Physics Research A, vol. 603, no. 3, pp. 504–509, 2009.
[30]
S. Subbuthai, P. Sahoo, R. Ananthanarayanan, A. Nageswara Rao, and R. V. Subba Rao, “Feasibility studies for the detection of third phase during reprocessing of fast reactor fuel,” Journal of Radioanalytical and Nuclear Chemistry, vol. 291, no. 2, pp. 879–883, 2012.
[31]
T. Kamei and A. Serizawa, “Measurement of 2-dimensional local instantaneous liquid film thickness around simulated nuclear fuel rod by ultrasonic transmission technique,” Nuclear Engineering and Design, vol. 184, no. 2-3, pp. 349–362, 1998.
[32]
T. Inoue, “Actinide recycling by pyro-process with metal fuel FBR for future nuclear fuel cycle system,” Progress in Nuclear Energy, vol. 40, no. 3-4, pp. 547–554, 2002.
[33]
S. Normand, V. Kondrasov, G. Corre, and C. Passard, “PING: a new approach for nuclear fuel cycle instrumentation,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[34]
I. Badawy and W. A. EI-Gammal, “Measurement of low enriched uranium fuel pellets,” in Proceedings of the 16th National Conference on Radio Science, Cairo, Egypt, February 1999.
[35]
A. Gavron, L. E. Smith, and J. J. Ressler, “Analysis of spent fuel assemblies using a lead slowing down spectrometer,” Nuclear Instruments and Methods in Physics Research A, vol. 602, no. 2, pp. 581–587, 2009.
[36]
S. K. Das, C. S. Kedari, and S. C. Tripathi, “Spectrophotometric determination of trace amount of uranium (VI) in different aqueous and organic streams of nuclear fuel processing using 2-(5-bromo-2-pyridylazo-5-diethylaminophenol),” Journal of Radioanalytical and Nuclear Chemistry, vol. 285, no. 3, pp. 675–681, 2010.
[37]
A. I. Hawari, J. Chen, B. J. Su, and Z. X. Zhao, “Assessment of on-line burnup monitoring of pebble bed reactor fuel using passive gamma-ray spectrometry,” IEEE Transactions on Nuclear Science, vol. 49, no. 3, pp. 1249–1253, 2002.
[38]
U. Meier, J. Heinze, L. Lange, C. Hassa, L. Rackwitz, and T. Doerr, “Characterisation of the combustion performance of low emission fuel injectors with laser measurements,” CEAS Aeronautical Journal, vol. 3, no. 1, pp. 45–53, 2012.
[39]
A. P. Belian, L. C. Bourva, S. C. Kane, and A. R. Lebrun, “The use of Monte Carlo techniques for the calibration of IAEA safeguards instrumentation,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[40]
N. Peter, M. Koskelo, and M. Stein, “The role of the nuclear industry in advancing safeguards instrumentation,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[41]
A. M. Lafleur, W. S. Charlton, H. O. Menlove, and M. T. Swinhoe, “Comparison of fresh fuel experimental measurements to MCNPX calculations using self-interrogation neutron resonance densitometry,” Nuclear Instruments and Methods in Physics Research A, vol. 680, pp. 168–178, 2012.
[42]
L. V. East, E. R. Martin, T. L. Atwell, R. H. Augustson, and H. O. Menlove, “Automated nondestructive assay instrumentation for nuclear materials safeguards,” Nuclear Science, vol. 22, no. 1, pp. 739–743, 1975.
[43]
C. Willman, A. H？kansson, O. Osifo, A. B？cklin, and S. J. Sv？rd, “Nondestructive assay of spent nuclear fuel with gamma-ray spectroscopy,” Annals of Nuclear Energy, vol. 33, no. 5, pp. 427–438, 2006.
[44]
A. K. Khusainov, T. A. Antonova, V. V. Lysenko et al., “High resolution, portable gamma spectrometer not requiring liquid nitrogen cooling for field use for nuclear security and safeguards applications,” in Proceedings of the Nuclear Science Symposium Conference, Dresden, Germany, October 2008.
[45]
M. Swoboda, R. Arlt, V. Gostilo et al., “Spectral gamma detectors for hand-held radioisotope identification devices (RIDs) for nuclear security applications,” in Proceedings of the Nuclear Science Symposium, Medical Imaging Conference, Symposium on Nuclear Power Systems and the 14th International Workshop on Room Temperature Semiconductor X- and Gamma-Ray Detectors, pp. 4296–4302, Rome, Italy, October 2004.
[46]
D. H. Beddingfield, A. Beyerle, P. A. Russo, K. Ianakiev, D. T. Vo, and V. Dmitrenko, “High-pressure xenon ion chambers for gamma-ray spectroscopy in nuclear safeguards,” Nuclear Instruments and Methods in Physics Research A, vol. 505, no. 1-2, pp. 474–477, 2003.
[47]
T. F. Wang, S. M. Horne, R. A. Henderson, K. E. Roberts, and D. K. Vogt, “Exploring simultaneous single and coincident gamma-ray measurements for U/Pu assay in safeguards,” in Proceedings of the 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[48]
M. Marseguerra, E. Padovani, and S. A. Pozzi, “Use of the MCNP-Polimi code for time-correlation safeguards measurements,” Progress in Nuclear Energy, vol. 43, no. 1–4, pp. 305–311, 2003.
[49]
S. A. Pozzi and J. Segovia, “252Cf source-correlated transmission measurements and genetic programming for nuclear safeguards,” Nuclear Instruments and Methods in Physics Research A, vol. 491, no. 1-2, pp. 326–341, 2002.
[50]
P. Vermaercke, F. F. Arboccò, L. Sneyers, A. Leal, and M. Bruggeman, “Environmental monitoring for safeguards using k0-standardised neutron activation analysis,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[51]
T. L. Frazzini, “Application of automated analytical instrumentation to the determination of uranium and plutonium for nuclear safeguards measurements,” IEEE Transactions on Nuclear Science, vol. 29, no. 1, pp. 866–868, 1981.
[52]
Thomas H. Smith, Ronald J. Hall, and L. Donald Williams, “Analytic methods for fuel-cycle safety studies,” IEEE Transactions on Reliability, vol. R-25, no. 3, pp. 184–190, 1976.
[53]
L. Lu and J. Jiang, “Probabilistic safety assessment for instrumentation and control systems in nuclear power plants: an overview,” Journal of Nuclear Science and Technology, vol. 41, no. 3, pp. 323–330, 2004.
[54]
P. E. Fehlaul, “Integrated neutrod gamma-ray portal monitors for nuclear safeguards,” Nuclear Science, vol. 41, no. 4, pp. 922–926, 1994.
[55]
A. Letourneau, V.-M. Bui, M. Cribier et al., “Nucifer: a small electron-antineutrino detector for fundamental and safeguard studies,” in 2nd International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'11), Ghent, Belgium, June 2011.
[56]
R. Baskaran, V. Subramanian, J. Misra, R. Indira, P. Chellapandi, and B. Raj, “Aerosol characterization and measurement techniques towards SFR safety studies,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[57]
B. Cabrera-Palmer, D. Reyna, L. Sadler et al., “Advances towards readily deployable antineutrino detectors for reactor monitoring and safeguards,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[58]
B. B. Parsons and J. L. Wells, “Tamper and radiation resistant instrumentation for safeguarding special nuclear material,” IEEE Transactions on Nuclear Science, vol. NS-24, no. 1, pp. 616–620, 1976.
[59]
S. H. Lee, Y. G. No, M. G. Na, K. I. Ahn, and S. Y. Park, “Diagnostics of loss of coolant accidents using SVC and GMDH models,” IEEE Transactions on Nuclear Science, vol. 58, no. 1, pp. 267–276, 2011.
[60]
M. Gro？e, M. Steinbrück, J. Stuckert, A. Kastner, and B. Schillinger, “Application of neutron radiography to study material processes during hypothetical severe accidents in nuclear reactors,” Journal of Materials Science, vol. 47, no. 18, pp. 6505–6512, 2012.
[61]
M. G. Na, W. S. Park, and D. H. Lim, “Detection and diagnostics of loss of coolant accidents using support vector machines,” IEEE Transactions on Nuclear Science, vol. 55, no. 1, pp. 628–636, 2008.
[62]
M. G. Na, S. H. Shin, S. M. Lee et al., “Prediction of major transient scenarios for severe accidents of nuclear power plants,” IEEE Transactions on Nuclear Science, vol. 51, no. 2, pp. 313–321, 2004.
[63]
W. K. Lu and B. Zhao, “Preliminary evaluation of the effect of several management measures for the station blackout severe accident of the pressurized water reactor nuclear power plant,” in Proceedings of the International Conference on Information Systems for Crisis Response and Management (ISCRAM'11), pp. 455–460, Harbin, China, November 2011.
[64]
D. Patterson, “Application of a computerised alarm-analysis system to a nuclear power station,” Electrical Engineers, vol. 115, no. 12, pp. 1858–1864, 1968.
[65]
S. W. Cheon, S. H. Chang, H. Y. Chung, and Z. N. Bien, “Application of neural networks to multiple alarm processing and diagnosis in nuclear power plants,” IEEE Transactions on Nuclear Science, vol. 40, no. 1, pp. 11–20, 1993.
[66]
S. S. Choi, K. S. Kang, H. G. Kim, and S. H. Chang, “Development of an on-line fuzzy expert system for integrated alarm processing in nuclear power plants,” IEEE Transactions on Nuclear Science, vol. 42, no. 4, pp. 1406–1418, 1995.
[67]
S. W. Cheon, S. H. Chang, and H. Y. Chung, “Development strategies of an expert system for multiple alarm processing and diagnosis in nuclear power plants,” IEEE Transactions on Nuclear Science, vol. 40, no. 1, pp. 21–30, 1993.
[68]
G. Ducros, S. Bernard, M. P. Ferroud-Plattet, and O. Ichim, “Use of gamma spectrometry for measuring fission product releases during a simulated PWR severe accident: application to the VERDON experimental program,” in Proceedings of the 1st International Conference on Advancements in Nuclear Instrumentation, Measurement Methods and Their Applications (ANIMMA'09), Marseille, France, June 2009.
[69]
K. Mitev, R. T. sibranski, V. Avramov et al., “Measurements of 133I, 134Cs and 137Cs In environmental samples in Bulgaria after the Fukushima accident,” in Proceedings of the Nuclear Science Symposium and Medical Imaging Conference, Valencia, Spain, October 2011.
[70]
S. Endo, S. Kimura, T. Takatsuji, K. Nanasawa, T. Imanaka, and K. Shizuma, “Measurement of soil contamination by radionuclides due to the Fukushima Dai-ichi nuclear power plant accident and associated estimated cumulative external dose estimation,” Journal of Environmental Radioactivity, vol. 111, pp. 18–27, 2012.
[71]
H. Amano, M. Akiyama, B. Chunlei et al., “Radiation measurements in the Chiba Metropolitan Area and radiological aspects of fallout from the Fukushima Dai-ichi nuclear power plants accident,” Journal of Environmental Radioactivity, vol. 111, pp. 42–52, 2012.
[72]
F. Perrot, P. Hubert, C. Marquet et al., “Evidence of 131I and 134,137Cs activities in Bordeaux, France due to the Fukushima nuclear accident,” Journal of Environmental Radioactivity, vol. 114, pp. 61–65, 2012.
[73]
M. Paul, D. Fink, G. Hollos, A. Kaufman, W. Kutschera, and M. Magaritz, “Measurement of 129I concentrations in the environment after the Chernobyl reactor accident,” Nuclear Instruments and Methods in Physics Research B, vol. 29, no. 1-2, pp. 341–345, 1987.
[74]
J. Gasparro, M. Hult, K. Komura et al., “Measurements of 60Co in spoons activated by neutrons during the JCO criticality accident at Tokai-mura in 1999,” Journal of Environmental Radioactivity, vol. 73, no. 3, pp. 307–321, 2004.
[75]
V. A. Nikolaev, “Application of SSNTDs to investigations of radiation accident after-effects,” Radiation Measurements, vol. 25, no. 1–4, pp. 337–345, 1995.
[76]
C. Bernhardsson, I. Zvonova, C. R？？f, and S. Mattsson, “Measurements of long-term external and internal radiation exposure of inhabitants of some villages of the Bryansk region of Russia after the Chernobyl accident,” Science of the Total Environment, vol. 409, no. 22, pp. 4811–4817, 2011.
