Abstract
The salient features of the use of lead and lead-bismuth in the power-generating loops removing heat from the blanket of a tokamak reactor are set forth. The results of experimental and theoretical investigations and analysis in substantiation of the use of heavy liquid-metal coolants in systems converting the energy of a blanket in a tokamak reactor into electricity are presented.
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REFERENCES
V. V. Orlov, E. V. Murav’ev, V. I. Khripunov, et al., “Heavy coolants based on lead in the system for cooling and converting the energy of a thermonuclear reactor with magnetic confinement of plasma,” At. Énerg., 71, No.6, 506–511 (1990).
A. V. Beznosov, P. V. Romanov, S. A. Kuz’minykh, et al., “Experimental investigation of the characteristics of electrically insulating coatings on structural materials of systems for cooling a tokamak with liquid-metal coolants,” Vopr. At. Nauk. Tekh., Ser. Termoyad. Sintez, No. 1–2, 31–39 (1998).
V. N. Zakhvatov, “Experimental and computational substantiation of the application of lead coolant in the system for cooling a tokamak blanket,” Dissertation for the Degree of Candidate of Engineering Sciences, Nizhnii Novgorod State Technical University, Nizhnii Novgorod (2001).
S. S. Pinaev, “Investigations and substantiation of the application of lead-bismuth eutectic as a coolant for the blanket of a thermonuclear reactor,” Dissertation for the Degree of Candidate of Engineering Sciences, Nizhnii Novgorod State Technical University, Nizhnii Novgorod (2002).
A. Cardella and A. Lodato, ITER Port Limiter Analysis. ITER Report No. G 16 RI 20 97-10-22 F2, Garching, Germany (1997).
A. V. Beznosov, A. A. Butov, P. V. Romanov, et al., “Influence of thermocyclic loads on the characteristics of electrically insulating coatings on structural materials in loops cooling a blanket and diverter with liquid-metal coolants,” Vopr. At. Nauk. Tekh., Ser. Termoyad. Sintez, No. 2, 66–72 (1999).
J. Shercliff, J. Fluid Mech., 13, No.4, 513 (1962).
J. Shercliff, Theory of Electromagnetic Measurement of Flow Rates [Russian translation], Mir, Moscow (1965).
J. Shercliff, “The flow of conducting fluids in circular pipes under transverse magnetic fields,” J. Fluid Mech., 4, No.1, 644–666 (1956).
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Translated from Atomnaya Énergiya, Vol. 98, No. 2, pp. 111–118, February, 2005.
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Beznosov, A.V., Pinaev, S.S. & Murav’ev, E.V. Application of lead and lead-bismuth in the heat-removal systems of tokamak reactors. At Energy 98, 103–109 (2005). https://doi.org/10.1007/s10512-005-0177-7
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DOI: https://doi.org/10.1007/s10512-005-0177-7