ICONE11-36407 THERMOHYDRAULIC RESEARCH FOR THE CORE OF THE BREST-OD-300 REACTOR

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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

• Smirnov V.

  Fsue Rdipe Named After N. A. Dollezhal

• Sorokin A.

  Rf Src Ippe

• Filin A.

  FSUE RDIPE named after N. A. Dollezhal

• Leonov V.

  FSUE RDIPE named after N. A. Dollezhal

• Zhukov A.

  Rf Src Ippe

• Sila-Novitskiy A.

  FSUE RDIPE named after N. A. Dollezhal

• Efanov A.

  RF SRC IPPE

• Kuzina J.

  RF SRC IPPE

関連論文

• ICONE11-36406 EXPERIMENTAL AND CALCULATED VALIDATION OF THE BREST-OD-300 REACTOR NEUTRONIC CHARACTERISTICS
• 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
• ICONE11-36410 DEVELOPMENT OF NPP WITH THE BREST-OD-300 NPP WITH AN ONSITE FUEL CYCLE AT BELOYARSK NPP. IMPLEMENTATION OF THE INITIATIVE BY RUSSIAN FEDERATION PRESIDENT V. V. PUTIN
• ICONE11-36131 PROBLEMS THERMOHYDRAULIC FAST REACTORS WITH LIQUID METAL COOLING
• ICONE11-36413 CORROSION AND MECHANICAL PROPERTIES OF STRUCTURAL MATERIALS TO BE USED IN THE BREST-OD-300 REACTOR

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