Abstract
The paper deals with prospects for using micropins in VVÉR reactors in order to provide a radical improvement in station safety. The most efficient arrangement is direct micropin cooling by the water moderator in assemblies involving transverse flow around a micropin layer. That design provides neutron-physics and thermohydraulic characteristics similar to those of VVÉR reactors containing rod elements. The micropins do not require any change in the reactor design, and pin assemblies containing them may be built to be identical with those in traditional VVÉR reactors as regards dimensions, connecting units, and thermohydraulic and neutron-physics characteristics. The conditions occurring in major accidents show that such reactors containing micropins can provide radiation safety in any major accident, and it is particularly promising to use them to extend the working lives of first-generation power stations not fitted with pressurized vessels or sealed shells.
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References
D. Bedenig,High-Temperature Gas-Cooled Reactors [Russian translation], Atomizdat, Moscow (1975).
Yu. G. Degal'tsev, I. S. Mosevitskii, N. N. Ponomarev-Stepnoi, et al., “Experimental studies on coolant technology and fuel elements for HTGC reactors based on PG-100 helium loops and ampule channels” in:Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian] (1983), pp. 185–193.
V. N. Grebennik, “The state of research on high-temperature gas-cooled reactors in the USSR,”ibid. Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian] (1983), pp. 106–118.
A. S. Chernikov, Yu. V. Koshelev, and Z. A. Shokina, “Manufacture and quality control for microelements, fuel pins, and assemblies for HTGC reactors,”ibid. Aspects of Nuclear Science and Engineering, Atomic Hydrogen Power Engineering and Technology Series, Issue 2 [in Russian], (1983), Issue 2 (1979), pp. 160–177.
A. O. Gol'tsev, N. E. Kukharkin, I. S. Mosevitskii, et al., “A concept for safe pressurized-water reactors containing fuel assemblies based on HTGC microelements,”At. Energ.,75, Issue 6, 418–423 (1993).
E. I. Grishanin, E. E. Denisov, A. Ya. Lyubin, and L. N. Fal'kovskii, “A model for the coolant parameters in fuel assemblies for a light-water reactor containing microelements,”Tyazh. Mashinostroenie, No. 9, 11–10 (1996).
O. S. Vinogradov, I. P. Smirnov, and I. P. Tigarev, “Hydrodynamics of cassettes containing packed spheres,”Trudy TsKTI, Issue 145, 107–119 (1977).
N. M. Beskorovainyi, Yu. S. Belomyttsev, M. D. Abramovich, et al.,Constructional Materials for Nuclear Reactors [in Russian], Atomizdat, Moscow (1977).
A Design and Assessment Study of Gas Cooled Breeder Reactors, ENEA, Brussels (1972).
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Translated from Atomnaya Énergiya, Vol. 86, No. 6, pp. 443–449, June, 1999.
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Ponomarev-Stepnoi, N.N., Kukharkin, N.E., Khrulev, A.A. et al. Prospects for using microelements in VVÉR reactors. At Energy 86, 411–418 (1999). https://doi.org/10.1007/BF02673192
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DOI: https://doi.org/10.1007/BF02673192