Abstract
Reactor operators have to judge the state of the reactor. In the operator room they see the panels displaying data on the state of the reactor and decide on the action to be taken to operate safely and economically. A reactor surveillance system is complex enough to encounter errors, failures, or malfunctions. The present chapter deals with disturbances and anomalies: how to discover them, what are the possible consequences of the disturbances and anomalies. The investigation focuses on early anomalies which are often hard to detect. Because of their safety implications, we deal with coolant flow anomalies, small changes in the flow pattern, possible errors in the technical side, like an erroneous follower enrichment data or a false measurement. Our investigations are based on the techniques having discussed throughout the previous chapters. It is possible to exploit disturbances when we study the consequences of a known anomaly to characterize the reactor.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Notes
- 1.
In many cases it suffices to know that the ratio of the temperatures should be constant in time.
- 2.
This is the case when the core map is symmetric. Since symmetry offers additional check on the measured values usually the map is symmetric.
- 3.
Figure 7.10 is not included as details of the cleaning process are out of our scope.
- 4.
As to activity, see the Appendix.
- 5.
Non-metered assemblies are light yellow colored.
- 6.
Non-metered assemblies are light salmon colored.
- 7.
Non-metered assemblies are light salmon colored.
- 8.
\(E\{\varDelta T\}\) is the average \(\varDelta T\) of the measured assemblies.
- 9.
The average is zero, only one number is negative in position 218.
- 10.
For example assembly No. 65 is involved in seven microsectors and it has also a measured value. Its maximum and minimum value as well as the measured value is given in Table 7.3.
- 11.
Just look at the positions of control rods in the core and remember, around 30 control rods are capable of shutting down the energy production in the entire core.
- 12.
Reactor operators measure control rod position from the bottom.
References
Williams, M.M.R.: Random Processes in Nuclear Reactors. Pergamon, Oxford (1974)
Szatmáry, Z.: Les incertitudes d’origine technologique et les mesures neutroniques, Note 41, Cadarache (1993)
Gandini, A.: Equivalent generalized perturbation theory (EGPT). Ann. Nucl. Energy 13, 109–114 (1986)
Makai, M., Orechwa, Y.: Field reconstruction from measured values in symmetric volumes. Nuclear Eng. Des. 199, 289–301 (2000)
Makai, M.: Group theory applied to boundary value problems with applications to reactor physics. Nova Science, New York (2011)
Henshaw, J., McGurk, J.C., Sims, H.E., Tuson, A., Dickinson, S., Deshon, J.: A model of cheminstry and thermal hydraulics in PWR fuel crud deposit. J. Nucl. Mater. 353, 1–11 (2006)
Nuclear Fuel Behaviour in Loss-of-coolant Accident (LOCA) Conditions, State-of-the-art Report, OECD, NEA No. 6846 (2009)
Status Report on Spent Fuel Pools under Loss-of-Cooling and Loss-of-Coolant Accident Conditions, NEA/CSNI/R(2015)2. http://www.oecd-nea.org
Makai, M., Temesvári, E., Orechwa, Y.: Field reconstruction from measured values using symmetries, mathematics and computation 2001. Salt Lake City, Utah, USA, September (2001)
Végh, J., Pós,I., Horváth, Cs., Kálya, Z., Parkó, T.,Ignits, M.: VERONA V6.22 An enhanced reactor analysis tool applied for continuous core parameter monitoring at Paks NPP. Nucl. Eng. Design, 292, 261–276(2015)
Kerr, R.A., Freeman, T.R., Lucoff, D.M.: A method of measuring and evaluating the temperature coefficient in the at-power condition. Trans. Am. Nucl. Soc. 30, 713 (1978)
Aira, M.: Ringhals 4 - Mätning av Moderatortemperaturkoefficient vid 100 % Reaktoreffekt, Ringhals Vattenfall report 0670/99 (in Swedish). Ringhals Vattenfall AB, Väröbacka, Sweden (1999)
Carlson, M.: Ringhals 2–4 - Metod för utvärdering av MTK-Mätning vid MOC, Ringhals Vattenfall report 1605463 (in Swedish). Ringhals Vattenfall AB, Väröbacka, Sweden (2000)
Makai, M., Pór, G.: Estimation of the moderator temperature coefficient d\(\rho \)/dT in a VVER-440 PWR Unit. In: 17th Pacific Basin Nuclear Conference Cancún, Q.R., Mexico, October 24–30 (2010)
Demaziere, Ch., Pázsit, I.: Theoretical investigation of the MTC noise estimate in 1-D homogeneous systems. Ann. Nuclear Energy 29, 75 (2002)
ANS: Calculation and Measurement of the Moderator Temperature Coefficient of Reactivity for Water Moderated Power Reactors, an American National Standard, American Nuclear Society, ANSI/ANS-19.11-1997 (1997)
Borland, X.X.: Nucl. Sci. Eng. 121, 162–171 (1995)
Demaziere, Ch., Pázsit, I., Pór, G.: Evaluation of the boron dilution method for moderator temperature measurement. Nucl. Technol. 140, 147 (2002)
Makai, M., Kálya, Z., Nemes, I., Pos, I., Pór G.: Evaluating new methods for direct measurement of the Moderator Temperature Coefficient in nuclear power plants during normal operation. In: Proceedings of seventeenth Symposium of AER, p. 963-982, Yalta, Ukraine, 23–29 September (2007)
Pós, I.: C-PORCA 4.0 Version description and validation procedure. In: Sixth AER Symposium on VVER Reactor Physics and Reactor Safety. Kirkkonummi, Finland (1996)
Szatmáry, Z.: User’s Manual of Program RFIT, Reports KFKI-1991-13/G, KFKI-1991-14/G, KFKI-1991-15/G, KFKI-1991-16/G
Temesvári, E., Makai, M.: Verification of the PRINCE(w) Principal Component Program for WWERs. In: Proceedings of International Conference on Reactor Physics and Reactor Computations, Israel, January (1994)
Makai, M., Temesvári, E.: Evaluation of in-core temperature measurements by means of principal component methods. Nuclear Sci. Eng. 112, 66 (1992)
Makai M., Temesvári, E.: Evaluation of in-core measurements by means of principal component methods. In: Proceedings of Conference In-Core Instrumentation and In-Situ Measurement in Connection with Fuel Behaviour, Petten, Holland, October (1992)
Ortiz de Echevarria Diez, I. et al.: Criticality Assessment for PWR with a Mistake on the Fuel Reloading Sequence, Integrating Criticality, Safety into the Resurgence of Nuclear Power, September 19–22, 2005, American Nuclear Society, LaGrange Park, IL (2005)
Makai, M., Orechwa, Y.: Field reconstruction from measured values in symmetric volumes. Nucl. Eng. Des. 199, 289–301 (2000)
Author information
Authors and Affiliations
Corresponding author
Rights and permissions
Copyright information
© 2017 Springer International Publishing AG
About this chapter
Cite this chapter
Makai, M., Végh, J. (2017). Detection of Disturbances and Anomalies. In: Reactor Core Monitoring. Lecture Notes in Energy, vol 58. Springer, Cham. https://doi.org/10.1007/978-3-319-54576-9_7
Download citation
DOI: https://doi.org/10.1007/978-3-319-54576-9_7
Published:
Publisher Name: Springer, Cham
Print ISBN: 978-3-319-54575-2
Online ISBN: 978-3-319-54576-9
eBook Packages: EnergyEnergy (R0)