ICONE11-36405 FUEL CYCLE OF BREST REACTORS : Solution of the RW and non-proliferation problems

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概要

• 論文の詳細を見る
• 一般社団法人日本機械学会の論文

著者

• Orlov V.

  Fsue Rdipe Named After N. A. Dollezhal

• Orlov V.

  Fsue Rdipe

• Lopatkin A.

  FSUE RDIPE named after N. A. Dollezhal

• Glazov A.

  FSUE RDIPE

• Volk V.

  FSUE NRIIM

• Poluektov P.

  FSUE NRIIM

• Leontyev V.

  FSUE SSDI

• Karimov R.

  OJSC "SverdNIIkhimmash"

• Karimov R.

  Ojsc "sverdniikhimmash

• Lopatkin A.

  Fsue Rdipe

関連論文

• ICONE11-36406 EXPERIMENTAL AND CALCULATED VALIDATION OF THE BREST-OD-300 REACTOR NEUTRONIC CHARACTERISTICS
• ICONE11-36405 FUEL CYCLE OF BREST REACTORS : Solution of the RW and non-proliferation problems
• ICONE11-36412 NUCLEAR POWER DEVELOPMENT ON NEW CONCEPTS OF NUCLEAR REACTORS AND ASSOCIATED FUEL CYCLE. PRESIDENT PUTIN'S INITIATIVE
• ICONE11-36415 DETERMINISTIC SAFETY OF THE BREST REACTORS
• ICONE11-36414 MONONITRIDE URANIUM-PLUTONIUM FUEL OF FAST LEAD-COOLED REACTORS

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