Abstract
The results of optimizational neutron-physical and thermohydrulic calculations of the core of a modular high-temperature helium-cooled reactor with mobile spherical fuel elements are presented. A special structural feature of such fuel elements is that they contain fuel microelements with multilayered ceramic coatings capable of confining radioactive fission products at high temperatures with deep burnup of nuclear fuel. The thermal power of the reactor is 850 MW(t) with average power density 30 MW/m3 and helium temperature 1000°C at the core exit. This makes it possible to use such reactors to produce hydrogen by a cost-effective high-temperature process using steam conversion of methane and to generate electricity in a one-loop helium turbosystem with efficiency >45%.
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REFERENCES
R. G. Bogoyavlenskii, Hydrodynamics and Heat Transfer in High-Temperature Reactors with Spherical Fuel Elements, Atomizdat, Moscow (1978).
Yu. V. Kotov, V. V. Krotov, and G. A. Filippov, Equipment for Nuclear Electric-Power Plants, Mashinostroenie, Moscow (1982), pp. 111-122.
Ya. M. Kolotyrkin, A. Kh. Breger, and E. A. Borisov, “Complete power-and-radiation utilization of nuclear reactors,” in: Nuclear-Hydrogen Power Production and Technology, Atomizdat, Moscow (1979), No. 2, pp. 32-40.
N. A. Dollezhal', N. D. Zichko, I. Ya. Emel'yanov, et al., “Complete utilization of the power produced by nuclear reactors for multitonnage production in the nitrogen industry,” ibid., pp. 5-15.
N. G. Kodochigov, N. G. Kuzavkov, E. V. Marova, et al., “GT-MGR-an inherently safe reactor system with minimum environmental effects,” Izvest.Akad.Prom.Ékologii, No. 2, 14-19 (1999).
A. O. Gol'tsev, “Choice of the optimal fuel cycle for HTGR operating according to the OPAZ principle with uranium oxide based fuel,” Vopr.At.Nauk.Tekh., Ser.At.-Vodorod.Énerget.Tekhnol., No. 1(4), 34-38 (1978).
S. V. Popov, “Stationary thermophysics of HTGR with a bulk core,” ibid., pp. 21-24.
O. S. Vinogradov, I. P. Smirnov, and I. P. Tiganev, “Hydrodynamics of fuel assemblies with spherical fill,” Trudy TSKTI, No. 145, 107-119 (1977).
S. L. Baturin and Yu. I. Petrov, “New reactor for nuclear power plants,” Integral, No. 1, 10-11 (2003).
D. Fishlock, “South Africa aims to build a pebble bed reactor module next summer,” Nucl.Europe Wordscan, No. 3-4, 14-16 (1999).
A. O. Gol'tsev, “START4-computer program for performing a complete calculation of a nuclear reactor with arbitrary composition in the R-Z geometry,” in: Integrated Mathematical Models and Programs, MIFI, Moscow (1998), pp. 321-325.
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Filippov, G.A., Bogoyavlenskii, R.G., Ponomarev-Stepnoi, N.N. et al. Modular High-Temperature Helium-Cooled Nuclear Reactor with Spherical Fuel Elements for Electricity and Hydrogen Production. Atomic Energy 96, 152–158 (2004). https://doi.org/10.1023/B:ATEN.0000030915.37320.26
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DOI: https://doi.org/10.1023/B:ATEN.0000030915.37320.26