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Dietmar Behrens, Sebastian Meyer, and Dieter Von Ehrenstein; Richard Donderer and Othfried Schumacher; Galina Davydova and Alexander Krayushkin, "Validation of MCNP for RBMK Criticality Calculations," Nuclear Technology, Vol. 114, No.1, pp. 1-11, April 1996.
Abstract - The Los Alamos National Laboratory Monte Carlo MCNP code is applied to critical experiments performed at the RBMK critical facility of the Russian Research Center "Kurchatov Institute," Moscow. The validation investigations are completed by whole-core criticality calculations of experiments at the Smolensk Unit 3 nuclear power plant as part of the startup procedure. The geometric model exploits the powerful capabilities of MCNP by precise representation of the fuel and different types of nonfuel channels, which add up to a detailed model of the critical facility and the RBMK core. Continuous-energy cross-sections tables are taken from the ENDF/B-IV and ENDF/B-VI libraries. As the most important uncertainty inherent to the experimental setup, the concentration of impurity isotopes in the graphite moderator is identified. Within the resulting error limits, k and the void effect are well reproduced with both cross-section libraries.
O. Yu. Novosel'skii, V. N. Filinov, and I. I. Kryuchkov, "Investigation of the Behavior of the Technological Channels of a RBMK Reactor Under Conditions of Heating During an Accident," Translated from Atomnaya Energiya, Vol. 78, No. 3, pp 155-160, March 1995.
E. Uspuras, A. Kaliatka, K. Almenas, "Verification of Design Characteristics of the RBMK- 150 Accident Confinement System," Nuclear Engineering and Design, Vol. 157, No. 3, pp. 353-361, 1995.
Abstract - The reactors of the Ignalina nuclear power plant (NPP) are protected by a pressure suppression type containment which because of its specialized nature is referred to as the accident confinement system (ACS). It differs from the standard pressure suppression containment in several respects. The differences include: not all of the primary cooling circuit is enclosed; it is made up of a number of semi-interconnected compartments; it utilizes ten separate pools of water for steam condensation; and it includes a clean air venting system. The first three features are similar to the confinement system used in the VVER-440/Mod213 Soviet built PWRs; the last feature seems to be unique. Other unique aspects, at least in the Western context, are the very sparse and incomplete documentation of the design characteristics of this system and the lack of analytical verification of the ACS effectiveness. The present paper provides an overview of design data regarding the ACS of the RBMK-1500 NPPs located at Ignalina, Lithuania.
B. I. Goncharov, V. N. Kozyr, A. V. Nosovskii, B. Ya. Oskolkov, V. V. Fomin, and E. A. Ivanov, "Effective Decrease of Radioactive Inert Gas Emissions from Nuclear Power Plants with RBMK Reactors," Translated from Atomnaya Energiya, Vol. 79, No. 4, pp. 311-313, October 1995.
B. E. Schmitt and Gl. V. Tsiklauri, "RBMK Pressure Tube Rupture Assessment," PNL-SA- 24831, 1994 RELAP 5th International Users Seminar, Baltimore, Maryland, August 29- September 1, 1994.
A. P. Sololov, E. S. Saakov, Yu. V. Garusov, and O. G. Chernikov, "Effect of Repositioning of Rhodium Direct-Charge Detectors in a RBMK-1000 Reactor on Fuel and Emitter-Material Burnup Coefficients," Translated from Atomnaya Energiya, Vol. 76, No. 6, pp. 470-473, June 1994.
V. A. Ryzhkov and L. B. Pitaeva, "Determination of the Deuterium Content in RBMK-1000 Coolant by the Method of Activation Analysis on Heavy Ions," Translated from Atomnaya Energiya, Vol. 77, No. 3, pp 222-224, September 1994.
V. I. Esikov, V. B. Karasev, O. Yu. Novosel'skii, V. N. Smolin, A. V. Shishov, V. P. Gal'berg, V. V. Stasenko, and E. D. Ustinov, "Investigation of the Hydraulic Characteristics of the Water-Leveling Pipes of RBMK-1000 Separator Drums," Translated from Atomnaya Energiya, Vol. 77, No. 5, pp. 334-340, November 1994.
V. B. Karasev, O. Yu. Novosel'skii, V. N. Smolin, and A. V. Shishov, "Methodological Questions Concerning Investigations of the Hydraulic Characteristics of the Water-Leveling Pipes of the Separator Drums in a RBMK Reactor," Translated from Atomnaya Energiya, Vol. 77, No. 5, pp. 329-334, November 1994.
Nuclear Safety Institute of Russian Academy of Science, " Russian RBMK Reactor Design Information," PNL-8937, November 1993.
G. H. Meriwether and J. P. McNeece, "Flux Stability and Power Control in the Soviet RBMK-1000 Reactors," PNL-8781, August 1993.
N. I. Laletin and V. A. Lyul'ka, "Stabilizing Effect of Control rods and Auxiliary Absorber Rods in an RBMK," Atomnaya Energiya, Vol. 74, No. 3, pp. 185-190, March 1993.
N. I. Laletin and V. a. Lyul'ka, "Reactivity Effects of Dryout in Several RBMK Multicells," Atomnaya Energiya, Vol. 74, No.3, pp. 179-185, March 1993.
N. I. Latetin, N. V. Sultanov, and V. A. Lyul'ka, "Surface-Harmonic Calculation of the RBMK-Reactor Polycells and Fuel Assemblies." Translated from Atomnaya Energiya, Vol. 74, No. 6, pp. 473-482, June 1993.
L. R. Pogosbekyan, D. A. Lysov, and L. L. Bronitskii, "Effect of Local Automatic control Rods on Three-Dimensional Calculations of the Power Distribution in an RBMK," Translated from Atomnaya Energiya, Vol. 74, No. 6, pp. 486-491, June 1993.
Yu. V. Mironov, Yu. M. Nikitin, T. I. Fomicheva, and E. A. Domoradov, "An Analysis of the Dynamics of the RBMK-1000 Reactor for Rupture of the Pressurized Collector at Low Power," Translated from Atomnaya Energiya, Vol. 75, No. 2, pp. 88-92, August 1993.
P. Guishani, A. R. Dastur and B. Chexal, "Stability Analysis of Spatial Power Distribution in RBMK-1000 Reactor," AECL-9424, December 1987.
Abstract - A simple model describing the linearized dynamics of a coupled neutronic and thermalhydraulic reactor system was used to analyze the stability of the radial and azmuthal power distribution in the boiling and spatially uncontrolled RBMK-1000 reactor (similar to Chernobyl-4). A parametric survey of stability of the power distribution was carried out over a range of power levels, flowrates and subcriticality of the power spatial modes. The significance of the various feedback mechanisms such as the moderator temperature, void, xenon and doppler reactivity are examined. A mop of instability trends in power spatial distribution with the mode subcriticality and the reactor power and flowrate was developed. It is predicted that all lower modes of reactor power spatial distribution of interest are unstable at all conditions in power and flowrate particularly at low power levels and flowrates.
N. A. Dollezhal, I. Y. Emel'yanov, Y. M. Cherkashov, V. P. Vasilevskii, L. N. Podlazov, V. V. Postnikov, A. P. Sirotkin, V. P. Kevrolev, and A. Y. Kramerov, "Some Characteristics of and Experience with the Operation of Nuclear Power Plants with RBMK-1000 High-Powered Water-Cooled Channel Reactors (RBMK)," Atomnaya Energiya, Vol. 54, No. 4, pp. 257-262, April, 1983.
N. A. Dollezhal, "Graphite-Water steam-generating reactor in the USSR," Nuclear Energy, Vol. 20, Oct., No. 5, pp. 385-390, 1981.
V. P. Angreev, A. V. Bondarenko, V. K. Vikulov, V. D. Kozyrev, R. M. Krasnogorov, V. F. Lyubchenko, F. M. Krasnogorov, V. F. Lyubchenko, V. V. Mal'tsev, Y. I. Mityaev, A. S. Oveshkov, E. I. Snitko, A. G. Sheinkman, and S. V. Shirokov, "Steam Effects and Reactivity Coefficients of the Beloyarsk Nuclear Power Station Reactors," Atomnaya Energiya, Vol. 50, No. 6, pp. 381-384, June 1981.
I. Y. Emel'yanov, L. N. Podlazov, A. N. Aleksakov, V. M. Panin, and B.V. Paraev, "Effect of the Shape of the Height Distribution of Neutrons on the Stability of a Reactor to Xenon Oscillations," Atomnaya Energiya, Vol. 50, No. 6, pp. 385-387, June 1981.
I. Y. Emel'yanov, L. N. Podlazov, A. N. Aleksakov, and V. M. Panin, "Effects of Neutron- Distribution Patterns on the Stability of a Power Reactor," Atomnaya Energiya, Vol. 48, No. 5, pp. 301-303, May 1980.
V. I. Pushkarev, A. d. Zhirnov, and A. P. Sirotkin, "Ways of Altering the Coefficients of Reactivity in RBMK Reactors," Atomnaya Energiya, Vol. 46, No. 6, pp. 386-389, June 1978.