ICONE11-36408 VALIDATION OF THE LEAD COOLANT TECHNOLOGY FOR BREST REACTORS

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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 Yu.

  Rf Src Ippe

• Leonov V.

  FSUE RDIPE named after N. A. Dollezhal

• Martynov P.

  RF SRC IPPE

• Gulevsky V.

  RF SRC IPPE

• Yemelyantseva Z.

  FSUE RDIPE named after N. A. Dollezhal

関連論文

• ICONE11-36415 DETERMINISTIC SAFETY OF THE BREST REACTORS
• ICONE11-36409 PRE-AND IN-PILE TESTS OF FUEL ELEMENT MOCKUPS FOR THE BREST-OD-300 REACTOR IN INDEPENDENT LEAD-COOLED CHANNEL OF THE BOR-60 REACTOR
• ICONE11-36408 VALIDATION OF THE LEAD COOLANT TECHNOLOGY FOR BREST REACTORS
• ICONE11-36407 THERMOHYDRAULIC RESEARCH FOR THE CORE OF THE BREST-OD-300 REACTOR
• ICONE11-36413 CORROSION AND MECHANICAL PROPERTIES OF STRUCTURAL MATERIALS TO BE USED IN THE BREST-OD-300 REACTOR

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