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Nuclear fuel cycle

Nuclear fuel cycle
Paper図書
B.S. Tomar [and five others], editorsSpringer[2023]<NG71-D6>
National Diet Library
  • Summary, etc....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 products during reactor operation, pos......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 ......rse on nuclear fuel cycle at postgraduate level
  • Contents...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 Produc......ment of Closed Fuel Cycle 1.7 International Scena...
  • Subject HeadingNuclear 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)
Paper図書
edited by Thomas J. DolanWoodhead Publishing, an imprint of Elsevier[2017]<NG41-D23>
National Diet Library
  • Summary, etc."Molten Salt Reactors is a comprehe......of molten salt reactor (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......nical issues - reactor physics, therm......ns -- thermal, fast, solid fuel, liquid fuel ... Specific d...... for engineers and scientists, and it can be used......duate students and advanced under......s. Molten Salt Reactors is the only c......he use of MSRs and thorium fuel, including stude...
  • Contents....2. MSR origin and research curta......s 1.4. Fissile fuels 1.5. Thorium fuel advantages 1.6. Liquid fuel MSR 1.7. Advan......ages of liquid fuel MSR 1.8. MSR d......l fundamentals and applications o......eat exchangers and materials embr...... 3.10. Summary and conclusions Ac......her Reading 4. Reactor physics of MSR......y distribution and Maxwell bolzma......4.7. Transport and diffusion of n......ics, dynamics, and neutron noise ...... 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 salt coolants 7....
  • Subject HeadingMolten salt reactors--Design and construction Molten salt reactors--Materials Th......ux Molten salt reactors. Molten salt fueled reactors. Thorium Isotopes.

Fast reactor fuel and fuel elements; proceedings. Edited by M. Dalle Donne, K. Kummerer [and] K. Schroeter.

Fast reactor fuel and fuel elements; proceedings. Edited by M. Dalle Donne, K. Kummerer [and] K. Schroeter.
Paper図書
Gesellschaft für Kernforschung mbH.1970.<NG71-52>
National Diet Library
  • Subject HeadingNuclear fuel elements -- Congresses. Fast reactors -- Congresses.
  • Note (General)...tion in Europe and the Kerntechnische Gesellscha...
  • Author Heading...nal Meeting on Fast Reactor and Fuel Elements (1970 : Karlsruhe)

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)
Paper図書
International Atomic Energy Agency1974.<Y530-1998-73>
National Diet Library

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)
Paper図書
International Atomic Energy Agency1974.<NG71-16>
National Diet Library
  • Subject HeadingNuclear fuels -- Congresses. Nuclear fuel elements -- Congresses. Fast reactors -- Congresses.
  • Author HeadingSymposium on Fuel and Fuel Elements for Fast Reactors, Brussels, 1973.

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)
Paper図書
VON DER HARDT, P.1971.
Other Libraries in Japan

Fast reactor fuel and fuel elements : proceedings of an international meeting

Fast reactor fuel and fuel elements : proceedings of an international meeting
Paper図書
held by the American Nuclear Society, Local Section in Europe, and the Kerntechnische Gesellschaft im Deutschen Atomforum, under the sponsorship of the Gesellschaft für Kernforschung mbH. Karlsruhe at the Kernforschungszentrum Karlsruhe, September 28-30, 1970 ; edited by M. Dalle Donne, K. Kummerer, K. SchroeterGesellschaft für Kernforschung mbH.1970
Other Libraries in Japan
  • Note (General)Text in English, French and German Includes bibliographic...

Fast reactor fuel and fuel elements; Proceeding of an international meeting.

Fast reactor fuel and fuel elements; Proceeding of an international meeting.
Paper図書
Donne, M.D.(ed.)/Kummerer, K.(ed.)/and othersGesellschaft fur Kernforschung mbH.1970.
Other Libraries in Japan

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)
Paper図書
Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)(Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia))1983.
Other Libraries in Japan

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)
Paper図書
Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia)(Ustav Jaderneho Vyzkumu CSKAE, Rez (Czechoslovakia))1982.
Other Libraries in Japan

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)
Paper図書
Oak Ridge National Laboratory(Oak Ridge National Laboratory)1981.
Other Libraries in Japan

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
Paper図書
held by the International Atomic Energy Agency in Brussels, 2-6 July 1973International Atomic Energy Agency1974
Other Libraries in Japan
  • Subject HeadingNuclear fuels -- Congresses Nuclear fuel elements -- Congresses Fast reactors -- Congresses
  • Subject Heading (ID)Nuclear fuels -- Congresses Nuclear fuel elements -- Congresses Fast reactors -- Congresses
  • Author HeadingSymposium on Fuel and Fuel Elements for Fast Reactors, Brussels, 1973 Internationa...

INVESTIGATION OF METHODS OF MANUFACTURING FAST REACTOR FUEL ELEMENT PINS FROM URANIUM MONOCARBIDE, MONONITRIDE, AND CARBONITRIDE. (ERDA ; ERDA-TR-9)

INVESTIGATION OF METHODS OF MANUFACTURING FAST REACTOR FUEL ELEMENT PINS FROM URANIUM MONOCARBIDE, MONONITRIDE, AND CARBONITRIDE. (ERDA ; ERDA-TR-9)
Paper図書
RESHETNIKOV, F.G.Energy Research and Development Administration(Energy Research and Development Administration)1975.
Other Libraries in Japan

LMFBR: LIQUID METAL FAST BREEDER REACTOR PROGRAM PLAN, ELEMENT 7, FUELS AND MATERIALS. (WASH ; WASH-1107(2ND.ED.))

LMFBR: LIQUID METAL FAST BREEDER REACTOR PROGRAM PLAN, ELEMENT 7, FUELS AND MATERIALS. (WASH ; WASH-1107(2ND.ED.))
Paper図書
1972.
Other Libraries in Japan

TOPICAL REPORT, FAST REACTOR MIXED CARBIDE FUEL ELEMENT DEVELOPMENT PROGRAM, HIGH POWER AND HEAT FLUX IRRADIATION OF URANIUM-PLUTONIUM CARBIDES. (GU ; GU-5294)

TOPICAL REPORT, FAST REACTOR MIXED CARBIDE FUEL ELEMENT DEVELOPMENT PROGRAM, HIGH POWER AND HEAT FLUX IRRADIATION OF URANIUM-PLUTONIUM CARBIDES. (GU ; GU-5294)
Paper図書
MONTGOMERY, M.H.1973.
Other Libraries in Japan

Dvourozmerny vypocet rychlostniho pole a vyvinu teplotniho pole pro kazetu rychleho reaktoru metodou konecnych prvku (UJV ; UJV-7240-T)

Dvourozmerny vypocet rychlostniho pole a vyvinu teplotniho pole pro kazetu rychleho reaktoru metodou konecnych prvku (UJV ; UJV-7240-T)
Paper図書
Schmid, J.Ustav Jaderneho Vyzkumu CSKAE1985.8.
Other Libraries in Japan
  • Translation of Title...velocity field and temperature fi......development in fast reactor fuel assembly

Dvourozmerny vypocet rychlostniho pole a vyvinu teplotniho pole pro kazetu rychleho reaktoru metodou konecnych prvku. II (UJV ; UJV-7242-T)

Dvourozmerny vypocet rychlostniho pole a vyvinu teplotniho pole pro kazetu rychleho reaktoru metodou konecnych prvku. II (UJV ; UJV-7242-T)
Paper図書
Schmid, J.Ustav Jaderneho Vyzkumu CSKAE1985.11.
Other Libraries in Japan
  • Translation of Title...velocity field and temperature fi......development in fast reactor fuel assembly. II

Automatizovane generovani siti pro kazetu rychleho reaktoru pri vypoctech rychlostnich a teplotnich poli metodou konecnych prvku. Cast II (UJV ; UJV-7241-T)

Automatizovane generovani siti pro kazetu rychleho reaktoru pri vypoctech rychlostnich a teplotnich poli metodou konecnych prvku. Cast II (UJV ; UJV-7241-T)
Paper図書
Schmid, J.Ustav Jaderneho Vyzkumu CSKAE1985.8.
Other Libraries in Japan
  • Translation of TitleAutomated mesh generation for fast reactor fuel assembly in ca......ating velocity and temperature fields by finite ...

IRRADIATION TESTING AND EVALUATION OF REFRACTORY METAL FUEL ELEMENTS OF 710 FAST REACTOR PROGRAM. FINAL REPORT. (GEMP ; GEMP-710)

IRRADIATION TESTING AND EVALUATION OF REFRACTORY METAL FUEL ELEMENTS OF 710 FAST REACTOR PROGRAM. FINAL REPORT. (GEMP ; GEMP-710)
Paper図書
NEWSOM, D.L.(et al.)1969.
Other Libraries in Japan

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)
Paper図書
HOFMANN, H.1973.
Other Libraries in Japan
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