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Title: Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems

Abstract

Russian controlled fusion program supposes development of a DEMO reactor design and participation in ITER Project. A solid breeder blanket of DEMO contains a ceramic lithium orthosilicate breeder and a beryllium multiplier. Test modules of the blanket are developed within the scope of ITER activities. Experimental models of module tritium breeding zones (TBZ), materials and fabrication technology of the TBZ, tritium reactor systems to analyse and process gas released from lithium ceramics are being developed. Two models of tritium breeding and neutron multiplying elements of the TBZ have been designed, manufactured and tested in IVV-2M nuclear reactor. Initial results of the in-pile experiments and outcome of lithium ceramics irradiation in a water-graphite nuclear reactor are considered to be a data base for development of the test modules and initial requirements for DEMO tritium system design. Influence of the tritium release parameters and hydrogen concentration in a purge gas on parameters of reactor system are discussed.

Authors:
; ; ; ; ; ; ; ; ;  [1]
  1. A.A. Bochvar Institute of Inorganic Materials (Russian Federation)
Publication Date:
OSTI Identifier:
20854229
Resource Type:
Journal Article
Journal Name:
Fusion Science and Technology
Additional Journal Information:
Journal Volume: 48; Journal Issue: 1; Other Information: Copyright (c) 2006 American Nuclear Society (ANS), United States, All rights reserved. http://epubs.ans.org/; Country of input: International Atomic Energy Agency (IAEA); Journal ID: ISSN 1536-1055
Country of Publication:
United States
Language:
English
Subject:
70 PLASMA PHYSICS AND FUSION TECHNOLOGY; BERYLLIUM; BREEDING BLANKETS; CERAMICS; DESIGN; FABRICATION; GRAPHITE; HYDROGEN; IRRADIATION; ITER TOKAMAK; LITHIUM; NEUTRONS; OPERATION; SILICATES; SOLIDS; THERMONUCLEAR REACTOR MATERIALS; TRITIUM

Citation Formats

Kapyshev, Victor K, Chernetsov, Mikhail Yu, Zhevotov, Sergej I, Kersnovskij, Alexandr Yu, Kolbasov, Boris N, Kovalenko, Victor G, Paltusov, Nikolaj P, Sernyaev, Georgeij A, Sterebkov, Juri S, and Zyryanov, Alexej P. Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems. United States: N. p., 2005. Web.
Kapyshev, Victor K, Chernetsov, Mikhail Yu, Zhevotov, Sergej I, Kersnovskij, Alexandr Yu, Kolbasov, Boris N, Kovalenko, Victor G, Paltusov, Nikolaj P, Sernyaev, Georgeij A, Sterebkov, Juri S, & Zyryanov, Alexej P. Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems. United States.
Kapyshev, Victor K, Chernetsov, Mikhail Yu, Zhevotov, Sergej I, Kersnovskij, Alexandr Yu, Kolbasov, Boris N, Kovalenko, Victor G, Paltusov, Nikolaj P, Sernyaev, Georgeij A, Sterebkov, Juri S, and Zyryanov, Alexej P. 2005. "Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems". United States.
@article{osti_20854229,
title = {Lithium Ceramic Blankets for Russian Fusion Reactors and Influence of Breeding Operation Mode on Parameters of Reactor Tritium Systems},
author = {Kapyshev, Victor K and Chernetsov, Mikhail Yu and Zhevotov, Sergej I and Kersnovskij, Alexandr Yu and Kolbasov, Boris N and Kovalenko, Victor G and Paltusov, Nikolaj P and Sernyaev, Georgeij A and Sterebkov, Juri S and Zyryanov, Alexej P},
abstractNote = {Russian controlled fusion program supposes development of a DEMO reactor design and participation in ITER Project. A solid breeder blanket of DEMO contains a ceramic lithium orthosilicate breeder and a beryllium multiplier. Test modules of the blanket are developed within the scope of ITER activities. Experimental models of module tritium breeding zones (TBZ), materials and fabrication technology of the TBZ, tritium reactor systems to analyse and process gas released from lithium ceramics are being developed. Two models of tritium breeding and neutron multiplying elements of the TBZ have been designed, manufactured and tested in IVV-2M nuclear reactor. Initial results of the in-pile experiments and outcome of lithium ceramics irradiation in a water-graphite nuclear reactor are considered to be a data base for development of the test modules and initial requirements for DEMO tritium system design. Influence of the tritium release parameters and hydrogen concentration in a purge gas on parameters of reactor system are discussed.},
doi = {},
url = {https://www.osti.gov/biblio/20854229}, journal = {Fusion Science and Technology},
issn = {1536-1055},
number = 1,
volume = 48,
place = {United States},
year = {Fri Jul 15 00:00:00 EDT 2005},
month = {Fri Jul 15 00:00:00 EDT 2005}
}