ICONE11-36414 MONONITRIDE URANIUM-PLUTONIUM FUEL OF FAST LEAD-COOLED REACTORS

スポンサーリンク

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

• Poluektov P.

  FSUE NRIIM

• Vatulin A.

  FSUE NRIIM

• Sila-Novitsky A.

  FSUE RDIPE named after N. A. Dollezhal

• Rogozkin B.

  FSUE VNIINM

• Ustinov O.

  Fsue Nriim

• Rogozkin B.

  Fsue Nriim

• Stepennova N.

  FSUE NRIIM

• Fedorov Yu.

  FSUE NRIIM

• Sukhanov L.

  FSUE NRIIM

関連論文

• 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
• ICONE11-36409 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
• ICONE11-36414 MONONITRIDE URANIUM-PLUTONIUM FUEL OF FAST LEAD-COOLED REACTORS
• ICONE11-36411 EXPERIMENTAL BASE, AVAILABLE AND UNDER CONSTRUCTION FOR R & D AIMED AT THE BREST REACTOR DESIGN SUBSTANTIATION

スポンサーリンク