WJNST  Vol.3 No.3 , July 2013
Possibility of Use of Noise Analysis for Identification of Reactor Conditions during Accidents
ABSTRACT

Knowledge and control of the thermo-hydraulic conditions in the reactor is required for the effective accident management. Dedicated and qualified for harsh environment instrumentation has to be in place for this purpose. Experience of the Fukushima Dai-ichi plant and the lessons learned from the European stress tests demonstrated that alternative and divers tools and methods are needed for the identification of reactor condition in extreme situations. In the paper the feasibility of development of an alternative accident monitoring via well-known noise diagnostics methods is proposed and demonstrated. The possibility of identification of reactor accident conditions using temperature and pressure fluctuations, noise of the neutron and gamma field is considered on the basis of research achievements in reactor noise. As an example the use of pressure fluctuations for accident monitoring is presented.




Cite this paper
T. Katona, "Possibility of Use of Noise Analysis for Identification of Reactor Conditions during Accidents," World Journal of Nuclear Science and Technology, Vol. 3 No. 3, 2013, pp. 96-105. doi: 10.4236/wjnst.2013.33017.
References
[1]   International Atomic Energy Agency, “Preliminary Findings and Lessons Learned from the 16 July 2007 earthquake at Kashiwazaki-Kariwa NPP,” Mission Report, Vienna, 2007.

[2]   IAEA, “International Fact Finding Expert Mission of the Nuclear Accident Following the Great East Japan Earthquake and Tsunami,” 2011. http://www.iaea.org/newscenter/news/2011/japanmission.html

[3]   T. J. Katona, “Possibility for Using Damage Indicators for Definition of Nuclear Power Plant Seismic Fragility,” Proceedings of the 8th International Conference on Structural Dynamics, Leuven, 2-4 July 2011, pp. 234-237.

[4]   Japanese Government, “Report of Japanese Government to IAEA Ministerial Conference on Nuclear Safety—Accident at TEPCO’s Fukushima Nuclear Power Stations,” 7 June 2011, pp. 44-49. http://www.iaea.org/newscenter/focus/fukushima/japan-report.

[5]   U. S. Nuclear Regulatory Commission, “Reactor Vessel Water Level Instrumentation in BWRs,” Washington DC, 1984.

[6]   Nuclear Regulatory Commission, Federal Register, Vol. 60, No. 175, 11 September 1995. http://www.gpo.gov/fdsys/pkg/FR-1995-09-11/html/95-22461.htm

[7]   D. D. Yue, “Use of PRA in Assessing BWR Vessel Level Instrumentation,” Transactions of the American Nuclear Society, Vol. 50, 1985, pp. 358-359.

[8]   U. S. Nuclear Regulatory Commission, “Resolution of Generic Safety Issues: Item B-60: Loose Parts Monitoring Systems (Rev. 1), NUREG-0933, Main Report with Supplements 1-33,” 2012. http://www.nrc.gov/reading-rm/doc-collections/nuregs/staff/sr0933/sec2/b60r1.html

[9]   H. M. Hashemian, “Sensor Performance and Reliability,” The Instrumentation, Systems, and Automation Society, 2005.

[10]   S. Kiss, S. Lipcsei and J. Végh, “Overview of Recent KFKI AEKI Activities in the Field of Plant Surveillance and Diagnostics, Power Plant Surveillance and Diagnostics: Applied Research with Artificial Intelligence,” Springer-Verlag, Berlin, Heidelberg, pp. 51-62

[11]   J. Végh, et al., “Implementation of New Reactivity Measurement System and New Reactor Noise Analysis Equipment in a VVER-440 Nuclear Power Plant,” IEEE Transactions on Nuclear Science,Vol. 57, No. 5, 2010, pp. 2689-2696.

[12]   P. Jirsa, “Algorithm for Monitoring the Height of Flooding of the Core, Technical Note,” Annals of Nuclear Energy, Vol. 24, No. 6, 1997, pp. 508-509.

[13]   D. Wach and G. Kosaly, “Investigation of the Joint Effect of Local and Global Driving Sources in Incore-Neutron Noise Measurements,” Atomkernenergie, Vol. 23, 1974, pp. 244-250.

[14]   T. Katona, L. Mesko, G. Por and J. Valko, “Some As- pects of the Theory of Neutron Noise,” Progress in Nuclear Energy, Vol. 9, 1982, pp. 209-222. doi:10.1016/0149-1970(82)90044-0

[15]   R. Kozma, “Studies on the Relationship between the Statistics of Void Fraction Fluctuations and Parameters of Two-Phase Flows,” International Journal of Multiphase Flow, Vol. 21, No. 2, 1995, pp. 241-251. doi:10.1016/0301-9322(94)00077-W

[16]   R. Kozma, H. van Dam and J. E. Hoogenboom, “Identification of Flow Patterns by Neutron Noise Analysis During Actual Coolant Boiling in Thin Rectangular Channels,” Nuclear Technology, Vol. 100, 1992, pp. 97-110.

[17]   R. Kozma, “Studies on the Relationship between the Statistics of Void Fraction Fluctuations and Parameters of Two-Phase Flows,” International Journal of Multiphase Flow, Vol. 21, No. 2, 1995, pp. 241-251. doi:10.1016/0301-9322(94)00077-W

[18]   R. Kozma, “Noise Investigations on Boiling Effects in a Simulated MTR-Type Fuel Assembly,” Delft University Press, Delft, 1992.

[19]   T. Katona and R. Kozma, “Problems of Estimation of the Thermohydraulic Parameters Using Neutron and Temperature Noise Signals,” Progress in Nuclear Energy, Vol. 21, 1988, pp. 431-445. doi:10.1016/0149-1970(88)90061-3

[20]   L. J. Kostic, J. Runkel and D. Stegemann, “Thermohydraulics Surveillance of Pressurized Water Reactors by Experimental and Theoretical Investigations of the Low Frequency Noise Field,” Progress in Nuclear Energy, Vol. 21, 1988, pp. 421-430. doi:10.1016/0149-1970(88)90060-1

[21]   T. H. J. J. van der Hagen and J. van der Voet, “Interpretation of Velocities Determined by Noise Analysis for Various Void Fractions and Flow Regimes in Two-Phase Flow,” Progress in Nuclear Energy, Vol. 21, 1988, pp. 565-573. doi:10.1016/0149-1970(88)90077-7

[22]   T. Katona and R. Kozma, “Studies to the Stochastic Theory of the Coupled Reactorkinetic-Thermohydraulic Systems: Analysis of Low-Frequency Noise Phenomena,”: Central Rearch Institute for Physics, Budapest, 1986, 18 p.

[23]   J. A. Thie, “Power Reactor Noise,” American Nuclear Society, La Grange Park, 1981.

[24]   R. Hampel, S. Fleischer, F. Drager and T. Maekawa, “Water Level Measurement System For Boiling Water Reactors Using Internal Gamma Radiation—Neural Network Application,” Proceedings of the 4th International FLINS Conference on Intelligent Techniques and Soft Computing in Nuclear Science and Engineering, Bruges, 28-30 August 2000, pp. 504-511.

[25]   Core Exit Temperature (CET), “Effectiveness in Accident Management of Nuclear Power Reactor,” Nuclear Energy Agency, Committee on the Safety of Nuclear Installations, 2010.

[26]   T. Katona, “Investigation of the Possibility of Identification of Coolant Condition via Analysis of Local Temperature Noise (in Russian),” KFKI, Budapest, 1978, p. 23.

[27]   R. Kozma and J. E. Hoogenboom, “Flow Measurements Using Noise Signals of Axially Displaced Thermocouples,” Annals of Nuclear Energy, Vol. 17, No. 9, 1990, pp. 493-513. doi:10.1016/0306-4549(90)90004-W

[28]   D. L. Nguyen, E. R. F. Winter and M. Greiner, “Sonic Velocity in Two-Phase Systems,” International Journal of Multiphase Flow, Vol. 7, No. 3, 1981, pp. 311-320. doi:10.1016/0301-9322(81)90024-0

[29]   J. L. Xu and T. H. Chen, “Acoustic Wave Prediction in Flowing Steam-Water Two-Phase Mixture,” International Journal of Heat and Mass Transfer, Vol. 43, No. 7, 2000, pp. 1079-1088. doi:10.1016/S0017-9310(99)00213-6

[30]   M. A. Grolmes and H. K. Fauske, “Propagation Characteristics of Compression and Rarefaction Pressure Pulses in One-Component Vapor-Liquid Mixtures,” Nuclear Engeneering and Design, Vol. 11, No. 1, 1970, pp. 137-142. doi:10.1016/0029-5493(70)90024-5

[31]   R. C. Mecredy and L. J. Hamilton, “The Effects of Nonequilibrium Heat, Mass and Momentum Transfer on Two-Phase Sound Speed,” International Journal of Heat and Mass Transfer, Vol. 15, No. 1, 1972, pp. 61-72. doi:10.1016/0017-9310(72)90166-4

[32]   L. I. Nikitin and N. V. Shariy, “On the Resonances of the Coolant in the Primary Circuit Loop of th VVERs,” In: , A. A. Gusarov, Eds., Dinamical Streses and Deformations in Elements of Components of Energetics, Nauka, Moscow, 1977, pp. 67-76.

[33]   J. A. Thie and J. A. Mullens, “Utilization of Pressure Noise for Reactor Anomaly Monitoring,” Proceeding of Specialist’s Meeting on Early Diagnosis of Failures in Primary System Components of Nuclear Power Plants, IAEA Report, Vienna, 1982.

[34]   T. Katona and I. Nagy, “Interpretation of the Low-Frequency Pressure Fluctuations in PWRs,” 16th Informal Meeting on Reactor Noise, Budapest, 18-20 May 1983, pp. 9-17.

[35]   I. Nagy and T. Katona, “Theoretical Investigation of the Low-Frequency Pressure Fluctuation in PWRs,” Progress in Nuclear Energy, Vol. 15, No. 1-3, 1985, pp. 671-683. doi:10.1016/0149-1970(85)90096-4

[36]   G. Grünwald, K. Junghanss and P. Liewers, “Investigation of Pressure Oscillations in a PWR Primary Circuit, Fourth Specialists Meeting on Reactor Noise Progress in Nuclear Energy, Vol. 15, 1985, pp. 651-659.

[37]   G. Grünwald, G. Hessel, P. Liewers and W. Schmitt, “Low Frequency Pressure Oscillations in a PWR,” Progress in Nuclear Energy, Vol. 9, 1982, pp. 569-579. doi:10.1016/0149-1970(82)90076-2

[38]   V. V. Bulavin, D. F. Gutsev and V. J. Pavelko, “The Experimental Definition of the Acoustic Standing Waves Series, Formed in the Coolant of the Primary Circuit of VVER-440 Type Reactor,” Progress in Nuclear Energy, Vol. 29, No. 3-4, 1995, pp. 153-170. doi:10.1016/0149-1970(95)00005-5

[39]   E. Altstadt, et al., “Development of Theoretical Oscillation-model for WWER-type Reactors on the basis of Finite-element Method and Adjustment of Model using Measurement of Vibrations at Original Plant (in German),” Rossendorf, FZR-196, 1997.

[40]   E. Altstadt, M. Scheffler and F.-P. Weiss, “Component Vibration of VVER-Reactors—Diagnostics and Modelling, Progress in Nuclear Energy, Vol. 29, No. 3-4, 1995, pp. 129-138. doi:10.1016/0149-1970(95)00002-2

[41]   K. N. Proskuryakov, “Application of Vibroacoustic Noise for Diagnostics of Technological Process in Nuclear Power Plants,” MEI, Moscow, 1999.

[42]   G. Mondjtaba, “Numerical and Experimental Justification for Acoustic Models of Coolant in Components of NPPs at WWER and PWR,” Ph.D. Thesis, 2004. http://www.dissercat.com/content/raschetno-eksperimentalnoe-obosnovanie-akusticheskikh-modelei-teplonositelya-v-oborudovanii

[43]   K. S. Novikov, “Numerical and Experimental Justifica- tion of Reasons for Increasing Vibrations of in Vessel Components and Fuel Assemblies in WWER-1000 Type Reactors,” Ph.D. Thesis, 2010. http://www.dissercat.com/content/raschetno-teoreticheskoe-i-eksperimentalnoe-obosnovanie-uslovii-rosta-vibratsiiv-vku-i-tvs

[44]   T. Katona, “Statistical Analysis of Subcooled Boiling Acoustic Noise,” KFKI, Budapest, 1981, p. 27.

 
 
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