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検索結果 19 件

Nuclear fuel cycle

Nuclear fuel cycle
紙図書
B.S. Tomar [and five others], editorsSpringer[2023]<NG71-D6>
国立国会図書館
  • 要約等...entire nuclear fuel cycle, which i......nium, thorium, and other nuclear ......erials, mining and milling of ore......pes of nuclear fuels and their physical......eraction among fuel and fission produc......ination, spent fuel reprocessing, ......nt, accounting and control of nuc......ear materials, and safety aspects involved in handling and transportation......ear scientists and engineers, you......g researchers, and postgraduate s......try in general and those engaged ......uclear science and technology in ...... as a textbook for a course on nuclear fuel cycle at postgraduate level
  • 内容細目Intro Foreword Preface A......ntents Editors and Contributors 1 The Nuclear Fuel Cycle: Introdu...... 1.1 What Is a Fuel Cycle? 1.2 Frontend and Backend of Fuel Cycle 1.2.1 Frontend of Fuel Cycle 1.2.2 Backend of Fuel Cycle 1.3 Cate......ies of Nuclear Fuel Cycle Based on......"Once-Through" Fuel Cycle 1.3.2 Twice-Through Fuel Cycle 1.3.3 Cl...... or "Recycled" Fuel Cycle 1.4 Open Versus Closed Fuel Cycle Options ......pact of Closed Fuel Cycle on Waste......ants of Closed Fuel Cycle 1.5.1 Closed Fuel Cycle Without ......y 1.5.2 Closed Fuel Cycle with MA ......y 1.5.3 Closed Fuel Cycle with MA and Fission Product Recovery 1.6 ...
  • 件名Nuclear fuels--Management Nuclear fuels--Safety measures Nuclear fuel elements Combustibles nucléaires--Ges...

Molten salt reactors and thorium energy (Woodhead Publishing series in energy)

Molten salt reactors and thorium energy (Woodhead Publishing series in energy)
紙図書
edited by Thomas J. DolanWoodhead Publishing, an imprint of Elsevier[2017]<NG41-D23>
国立国会図書館
  • 要約等"Molten Salt Reactors is a comprehen......(MSR) research and thorium fuel utilization. T......energy sources and to avoid pollu......on from fossil fuels. Light water reactors are complex, expensive, and vulnerable to ......am explosions, and hydrogen explo......heric pressure and high temperatu......en production, and other industri......ns -- thermal, fast, solid fuel, liquid fuel ... Specific d......um Molten Salt Forum. It can serv......as a reference for engineers and scientists, and it can be used as a textbook for graduate students and advanced under......s. Molten Salt Reactors is the only co......essential text for anyone reviewing the use of M...
  • 内容細目... approximation and the point kine......lics of liquid-fueled MSRs / Alessandro Pini 6.1. In...... Heat transfer and pressure losse......alt 7.2. Solid fuels with molten s......s 7.3. Thorium fuel cycle 7.4. Mod......sing of liquid fuel / Jan Uhlir 8.......f fresh liquid fuel for MSR 8.3. Repro......hnology of MSR fuel 8.4. Gas extra......onment, waste, and resources / Ma......m ThorCon type reactors 9.4. Resource ......nproliferation and safeguards asp......cts of the MSR fuel cycle / Carl H......nproliferation and nuclear safegu......ion advantages and disadvantages ...... improving MSR fuel cycle proliferation resistanc...
  • 件名Molten salt reactors--Design and construction Molten salt reactors--Materials Tho......ux Molten salt reactors. Molten salt fueled reactors. Thorium Isotopes.

Fissile material management strategies for sustainable nuclear energy : proceedings of an IAEA Technical Meeting on Fissile Material Management Strategies for Sustainable Nuclear Energy, held in Vienna, 12-15 September 2005. (Proceedings series)

Fissile material management strategies for sustainable nuclear energy : proceedings of an IAEA Technical Meeting on Fissile Material Management Strategies for Sustainable Nuclear Energy, held in Vienna, 12-15 September 2005. (Proceedings series)
紙図書
International Atomic Energy Agency2007.<YU111-B683>
国立国会図書館全国の図書館
  • 内容細目FRONT END FUEL CYCLE STRATEGI...... 1: Uranium demand and supply up to 2......: Availability and appraisal of m......ustralia, Asia and Africa / D.B. ......of exploration and production act......um exploration and mining: Status and related challe......Uranium supply and production sce......rfenov Thorium and unconventional......tchie BACK END FUEL CYCLE STRATEGI......ent strategies for sustainable nu......ergy: Back end fuel cycle options ......al.] Modelling for nuclear materi......in the nuclear fuel cycle / M. Ceyhan Forecast of fissil......of the nuclear fuel cycle / K. Fuk......abase of spent fuel inventories and management / ...
  • 件名...esses. Nuclear fuels -- Management......es. Uranium as fuel -- Congresses.
  • 著者標目...ent Strategies for Sustainable Nuclear Energy (2...

Overview of past and current activities on fuels for fast reactors at the Institute for Transuranium Elements

Overview of past and current activities on fuels for fast reactors at the Institute for Transuranium Elements
デジタル記事
2009-07Journal of Nuclear Materials392 2p.133-138
全国の図書館
  • 件名Nuclear Energy and Engineering General Materials Science Nuclear and High Energy Physics
  • 参照.../mml:math>NMR, and<mml:math xmlns:mml="http://ww...
  • 著者標目A. Fernandez J. McGinley J. Somers M. Wa...

Fuel and fuel elements for fast reactors : proceedings of a symposium on fuel and fuel elements for fast reactors held by the International Atomic Energy Agency in Brussels, 2-6 July 1973. (Proceedings series)

Fuel and fuel elements for fast reactors : proceedings of a symposium on fuel and fuel elements for fast reactors held by the International Atomic Energy Agency in Brussels, 2-6 July 1973. (Proceedings series)
紙図書
International Atomic Energy Agency1974.<Y530-1998-73>
国立国会図書館

Fuel and fuel elements for fast reactors; proceedings of a Symposium ... held by the International Atomic Energy Agency in Brussels, 2-6 July 1973. (International Atomic Energy Agency. Proceedings series)

Fuel and fuel elements for fast reactors; proceedings of a Symposium ... held by the International Atomic Energy Agency in Brussels, 2-6 July 1973. (International Atomic Energy Agency. Proceedings series)
紙図書
International Atomic Energy Agency1974.<NG71-16>
国立国会図書館
  • 件名Nuclear fuels -- Congresses. Nuclear fuel elements -- Congresses. Fast reactors -- Congresses.
  • 著者標目Symposium on Fuel and Fuel Elements for Fast Reactors, Brussels, 1973.

Fuel and fuel elements for fast reactors : proceedings of a Symposium on fuel and fuel elements for fast reactors

Fuel and fuel elements for fast reactors : proceedings of a Symposium on fuel and fuel elements for fast reactors
紙図書
held by the International Atomic Energy Agency in Brussels, 2-6 July 1973International Atomic Energy Agency1974
全国の図書館
  • 件名Nuclear fuels -- Congresses Nuclear fuel elements -- Congresses Fast reactors -- Congresses
  • 件名（識別子）Nuclear fuels -- Congresses Nuclear fuel elements -- Congresses Fast reactors -- Congresses
  • 著者標目Symposium on Fuel and Fuel Elements for Fast Reactors, Brussels, 1973 International...

Automated mesh generation for fast reactor fuel assembly in calculating velocity and temperature fields by finite element method (UJV UJV-6442-T)

Automated mesh generation for fast reactor fuel assembly in calculating velocity and temperature fields by finite element method (UJV UJV-6442-T)
紙図書
Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)(Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia))1983.
全国の図書館

Mesh generation for fast reactor fuel assembly in velocity and temperature field calculations using finite element method (UJV UJV-6232-T)

Mesh generation for fast reactor fuel assembly in velocity and temperature field calculations using finite element method (UJV UJV-6232-T)
紙図書
Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)(Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia))1982.
全国の図書館

DEVELOPMENT OF VARIABLE-WIDTH RIBBON HEATING ELEMENTS FOR LIQUID-METAL AND GAS-COOLED FAST BREEDER REACTOR FUEL-PIN SIMULATORS (ORNL ORNL-5690)

DEVELOPMENT OF VARIABLE-WIDTH RIBBON HEATING ELEMENTS FOR LIQUID-METAL AND GAS-COOLED FAST BREEDER REACTOR FUEL-PIN SIMULATORS (ORNL ORNL-5690)
紙図書
Oak Ridge National Laboratory(Oak Ridge National Laboratory)1981.
全国の図書館

SOME BR2 IRRADIATION DEVICES FOR FAST REACTOR FUEL AND FUEL ELEMENTS (EUR EUR-4632-E)

SOME BR2 IRRADIATION DEVICES FOR FAST REACTOR FUEL AND FUEL ELEMENTS (EUR EUR-4632-E)
紙図書
VON DER HARDT, P1971.
全国の図書館

VENTING DEVICE FOR SODIUM COOLED FAST CERAMIC REACTOR FUEL ELEMENTS.:DESIGN STUDY AND OUT OF PILE TESTS (RT RT-ING-(70)29; RVT-SEC-(70)36)

VENTING DEVICE FOR SODIUM COOLED FAST CERAMIC REACTOR FUEL ELEMENTS.:DESIGN STUDY AND OUT OF PILE TESTS (RT RT-ING-(70)29; RVT-SEC-(70)36)
紙図書
BERTONCELLO, G.(et al.)1970.
全国の図書館

DEVELOPMENT OF SAFEGUARDS PROCEDURES AND SIMULATION OF FISSILE MATERIAL FLOW FOR AN ALKEM TYPE PLANT FABRICATING PLUTONIUM FUEL ELEMENTS FOR FAST BREEDER REACTORS (KFK KFK-1110)

DEVELOPMENT OF SAFEGUARDS PROCEDURES AND SIMULATION OF FISSILE MATERIAL FLOW FOR AN ALKEM TYPE PLANT FABRICATING PLUTONIUM FUEL ELEMENTS FOR FAST BREEDER REACTORS (KFK KFK-1110)
紙図書
DROSSELMEYER, E.(et al.)1971.
全国の図書館

IRRADIATION-INDUCED BIAXIAL CREEP BEHAVIOUR OF FUEL-ELEMENT CLADDINGS FOR FAST REACTORS: EXPERIMENTAL AND THEORETICAL RESULTS (KFK KFK-1017)

IRRADIATION-INDUCED BIAXIAL CREEP BEHAVIOUR OF FUEL-ELEMENT CLADDINGS FOR FAST REACTORS: EXPERIMENTAL AND THEORETICAL RESULTS (KFK KFK-1017)
紙図書
LAUE, H.J.(et al.)1969.
全国の図書館

EXPERIMENTAL INVESTIGATIONS ON COOLANT CROSS MIXING AND PRESSURE DROP IN ROD BUNDLES WITH HELICAL SPACERS. INFLUENCE OF THE RESULTS ON THE DESIGN OF FUEL ELEMENTS FOR SODIUM-COOLED FAST REACTORS (EURFNR EURFNR-1161)

EXPERIMENTAL INVESTIGATIONS ON COOLANT CROSS MIXING AND PRESSURE DROP IN ROD BUNDLES WITH HELICAL SPACERS. INFLUENCE OF THE RESULTS ON THE DESIGN OF FUEL ELEMENTS FOR SODIUM-COOLED FAST REACTORS (EURFNR EURFNR-1161)
紙図書
HOFMANN, H1973.
全国の図書館

PROPERTIES AND BEHAVIOUR OF IRRADIATED STEELS FOR FAST REACTOR FUEL ELEMENT CLADDING (A-CONF A-CONF.49-P-453)

PROPERTIES AND BEHAVIOUR OF IRRADIATED STEELS FOR FAST REACTOR FUEL ELEMENT CLADDING (A-CONF A-CONF.49-P-453)
紙図書
AGAPOVA, N.P
全国の図書館

PLUTONIUM ALLOYS AND COMPOUNDS FOR SOLID FUEL OR CONTROL ELEMENTS IN FAST REACTORS (LWS LWS-24898(DEL.))

PLUTONIUM ALLOYS AND COMPOUNDS FOR SOLID FUEL OR CONTROL ELEMENTS IN FAST REACTORS (LWS LWS-24898(DEL.))
紙図書
FULRATH,R.M
全国の図書館

VENTING DEVICE FOR SODIUM COOLED FAST CERAMIC REACTOR FUEL ELEMENTS.:DESIGN STUDY AND OUT OF PILE TESTS (CNEN CNEN-RT-ING(70)29)

VENTING DEVICE FOR SODIUM COOLED FAST CERAMIC REACTOR FUEL ELEMENTS.:DESIGN STUDY AND OUT OF PILE TESTS (CNEN CNEN-RT-ING(70)29)
紙図書
BERTONCELLO, G
全国の図書館

FAST REACTOR MIXED CARBIDE FUEL ELEMENT DEVELOPMENT.:THE DESIGN AND FABRICATION OF THREE (UPU)C PILOT EXPERIMENTS FOR EB (UNC UNC-5137)

FAST REACTOR MIXED CARBIDE FUEL ELEMENT DEVELOPMENT.:THE DESIGN AND FABRICATION OF THREE (UPU)C PILOT EXPERIMENTS FOR EB (UNC UNC-5137)
紙図書
CIHI, J
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