Development of RBMK in-reactor control
The most important component of reliable and safe operation of a nuclear reactor is controlling its distributed and general parameters. Different in-reactor control systems used previously and currently in NPP with RBMK are examined. The means for controlling the power release in the reactor core ar...
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| Published in: | Atomic energy (New York, N.Y.) Vol. 114; no. 4; pp. 237 - 242 |
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| Main Authors: | , , , , |
| Format: | Journal Article |
| Language: | English |
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01-08-2013
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| Abstract | The most important component of reliable and safe operation of a nuclear reactor is controlling its distributed and general parameters. Different in-reactor control systems used previously and currently in NPP with RBMK are examined. The means for controlling the power release in the reactor core are examined and the methods for reconstructing the power release in RBMK are reviewed briefly. |
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| AbstractList | The most important component of reliable and safe operation of a nuclear reactor is controlling its distributed and general parameters. Different in-reactor control systems used previously and currently in NPP with RBMK are examined. The means for controlling the power release in the reactor core are examined and the methods for reconstructing the power release in RBMK are reviewed briefly.[PUBLICATION ABSTRACT] The most important component of reliable and safe operation of a nuclear reactor is controlling its distributed and general parameters. Different in-reactor control systems used previously and currently in NPP with RBMK are examined. The means for controlling the power release in the reactor core are examined and the methods for reconstructing the power release in RBMK are reviewed briefly. |
| Audience | Academic |
| Author | Aleksandrov, S. I. Yurkin, G. V. Yakunin, I. S. Postnikov, V. V. Sviridenkov, A. N. |
| Author_xml | – sequence: 1 givenname: V. V. surname: Postnikov fullname: Postnikov, V. V. organization: Dollezhal Research and Development Institute of Power Engineering (NIKIET) – sequence: 2 givenname: S. I. surname: Aleksandrov fullname: Aleksandrov, S. I. organization: Dollezhal Research and Development Institute of Power Engineering (NIKIET) – sequence: 3 givenname: A. N. surname: Sviridenkov fullname: Sviridenkov, A. N. organization: Dollezhal Research and Development Institute of Power Engineering (NIKIET) – sequence: 4 givenname: G. V. surname: Yurkin fullname: Yurkin, G. V. organization: Dollezhal Research and Development Institute of Power Engineering (NIKIET) – sequence: 5 givenname: I. S. surname: Yakunin fullname: Yakunin, I. S. organization: Dollezhal Research and Development Institute of Power Engineering (NIKIET) |
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| Cites_doi | 10.1007/s10512-012-9588-4 10.1007/s10512-013-9685-z 10.1007/BF01121793 |
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| DOI | 10.1007/s10512-013-9703-1 |
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| Keywords | Axial Distribution Fuel Assembly Radial Detector Power Release Automatic Stabilization |
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| References | BöckHMiniature detectors for reactor in core neutron flux monitoringAt. Energy Rev.197614187132 V. V. Postnikov, O. K. Egorov, Yu. V. Rybakov, et al., “Experience in using Compton emission detectors with HfO2 emitters,” in: Int. Symp. Measurements Important for Safety in Reactors (2002), pp. 5-1–5-8. BronitskiiLLPostnikovVVProshinVAReconstruction of the three-dimensional power release field in RBMK-1500 fuel assembliesAt. Énerg.1991704246248 Emel’yanovIYEperinAPAleksakovANAutomatic system for controlling the power distribution in a power reactorAt. Énerg.1980496357363 RBMK Channel Power Reactor, FGUP NIKIET, Moscow (2006). GorelovAIEfanovAINazaryanVGStatic analysis of analog regulators of power release distribution in nuclear reactorsAt. Énerg.1989662818510.1007/BF01121793 FilipchukEVPotapenkoPTPostnikovVVControl of the Neutron Field in a Nuclear Reactor1981MoscowEnergoizdat DollezhalNAEmel’yanovIYChannel Nuclear Power Reactor1980MoscowAtomizdat LysikovBVKondrat’evVVMikhailovMNDevelopment of complex automation systems of nuclear power plantsAt. Énerg.20121131131910.1007/s10512-012-9588-4 BronitskiiLLLobodaKVPostnikovVVAlgorithm for reconstructing the axial distribution of the neutron flux according to signals from point and extended detectorsAt. Énerg.1991714303308 AleksandrovSIKonopatovRVPostnikovVVApplication of gamma-neutron ionization chambers for monitoring the distribution of the neutron flux density, power release and power release in RBMK-1000At. Énerg.20081033182186 BronitskiiLLZastroginANKuznetsovSPOn the determination of the critical power of RBMK-1500 fuel assembliesAt. Énerg.1986603163166 AleksandrovSIDavydovVKPostnikovVVTaking account of the detector spectral sensitivity in algorithms of the RBMK SKALA-mikro systemAt. Énerg.20101093133138 AleksandrovSIBol’shovAADemenkoIPCalibration of in-reactor detectors and evaluation of the error of computational methods of information-measurement system SKALA-mikro of RBMK-1000At. Énerg.2013114211311510.1007/s10512-013-9685-z IY Emel’yanov (9703_CR3) 1980; 49 AI Gorelov (9703_CR4) 1989; 66 LL Bronitskii (9703_CR8) 1991; 71 NA Dollezhal (9703_CR1) 1980 BV Lysikov (9703_CR9) 2012; 113 SI Aleksandrov (9703_CR10) 2013; 114 H Böck (9703_CR7) 1976; 14 SI Aleksandrov (9703_CR11) 2008; 103 9703_CR6 9703_CR5 SI Aleksandrov (9703_CR14) 2010; 109 LL Bronitskii (9703_CR13) 1986; 60 EV Filipchuk (9703_CR2) 1981 LL Bronitskii (9703_CR12) 1991; 70 |
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| SubjectTerms | Control systems Corrosion Detectors Electrodes Hadrons Heavy Ions Monitoring systems Nuclear Chemistry Nuclear Energy Nuclear Physics Nuclear reactors Physics Physics and Astronomy R&D Radiation Reactors Regulation Research & development Safety Sensors Studies |
| Title | Development of RBMK in-reactor control |
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