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Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.].
Pellet-clad interaction in water reactor fuels : seminar proceedings, Aix-en-Provence, France, 9-11 March 2004 / hosted by CEA Cadarache, DEN, DEC ; in co-operation with EDF ... [et al.].
Estensione 548 p. : ill. ; 27 cm.
Disciplina 621.48335
Accesso ente Commissariat à l'énergie atomique, Cadarache
Direction de l'énergie nucléaire
Council for Exceptional Children.Division for Early Childhood
Electricité de France
OECD Nuclear Energy Agency
ISBN 9264011579
9789264011571
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. NYU-000563375
Materiale a stampa
Lo trovi qui: New York University
Laser isotope separation in atomic vapor [electronic resource] / P.A. Bokhan ... [et al.].
Laser isotope separation in atomic vapor [electronic resource] / P.A. Bokhan ... [et al.].
Disciplina 621.48335
Accesso persona Bokhan, P. A.
Accesso ente ebrary, Inc.
Wiley Online Library (Online service)
ISBN 9783527406210
3527406212
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UMICH-014333095
Materiale a stampa
Lo trovi qui: University of Michigan Ann Arbor
Thorium energy for the world : proceedings of the ThEC13 Conference, CERN, Globe of Science and Innovation, Geneva, Switzerland, October 27-31, 2013 / Jean-Pierre Revol [and five others], editors
Thorium energy for the world : proceedings of the ThEC13 Conference, CERN, Globe of Science and Innovation, Geneva, Switzerland, October 27-31, 2013 / Jean-Pierre Revol [and five others], editors
Estensione 1 online resource (442 pages) : illustrations, photographs, tables
Disciplina 621.48335
Accesso persona Revol, Jean-Pierre, editor
ISBN 9783319265407
9783319265421
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UALBERTA-8113946
Materiale a stampa
Lo trovi qui: University of Alberta / NEOS Library Consortium
Problems in the accounting for and safeguarding of special nuclear materials : hearing before the Subcommittee on Energy and the Environment of the Committee on Small Business, House of Representatives; Ninety-fourth Congress, second session; Washington, D.C.; April 26, May 7 and 29, 1976
Problems in the accounting for and safeguarding of special nuclear materials : hearing before the Subcommittee on Energy and the Environment of the Committee on Small Business, House of Representatives; Ninety-fourth Congress, second session; Washington, D.C.; April 26, May 7 and 29, 1976
Creatore [United States. Congress. House. Committee on Small Business. Subcommittee on Energy and Environment]
Estensione 1 online resource (iii, 1655 pages) : illustrations
Disciplina 621.48335
Genere/Forma Inventories
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. NYU-006951308
[United States. Congress. House. Committee on Small Business. Subcommittee on Energy and Environment]  
Materiale a stampa
Lo trovi qui: New York University
Mixed oxide fuel (Mox) exploitation and destruction in power reactors / edited by Erich R. Merz, Carl E. Walter, Gennady M. Pshakin
Mixed oxide fuel (Mox) exploitation and destruction in power reactors / edited by Erich R. Merz, Carl E. Walter, Gennady M. Pshakin
Creatore [NATO Advanced Research Workshop on Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors (1994 : Obninsk, Russia)]
Estensione 1 online resource (xv, 309 pages).
Disciplina 621.48335
Accesso persona Merz, Erich R.
Walter, Carl E.
Pshakin, Gennady M.
ISBN 9789401722889
9401722889
9789048145492
904814549X
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto 1. Management of Plutonium in Russia -- 2. Overview Long-Term Disposition Options for Plutonium Rational Management of Excess Weapons Plutonium -- 3. Basic Technological Solutions for Plutonium Management at the RT-2 Plant -- 4. Disposition of Surplus Separated Plutonium Influence of Interim Storage of Plutonium -- 5. Security and Safeguards Aspects of Nuclear Material Handling in Russia -- 6. Security and Safeguards Aspects of Plutonium Facilities in BNFL, UK -- 7. A Perspective on Safeguarding and Monitoring Excess Military Plutonium -- 8. Plutonium Burning in CANDU -- 9. The Safety Criteria and VVER Core Modification for Weapon Plutonium Utilization -- 10. A Plutonium-Fueled PWR 2000 -- 11. Potential for Use of All-MOX Fuel in Existing and Evolutionary/Advanced LWRs in the United States -- 12. Use of Mixed Oxide Fuel in Existing Light Water Reactors in Germany -- 13. Japanese Nuclear Fuel Recycle Plutonium Utilization-Policy -- 14. Use of Plutonium in the UK -- 15. MOX Fuel Utilization in Existing German LWRs: Design and Safety Aspects, Core Performance, and Irradiation Experience -- 16. Development of Fast Reactor Core for Weapons Grade Plutonium Utilization -- 17. Irradiation Experience and Post-Irradiation Examination Results for MOX Pellet Fuel of Fast Reactors -- 18. Commercial MOX Fuel Fabrication and Irradiation Experience in Belgium -- 19. Plutonium Utilization Experience in Japan -- 20. Development and Fabrication Experience of MOX Fuel in the UK -- 21. Manufacturing Experience on Pelletized Mixed Oxide (MOX) Fuel for Fast Reactors -- 22. MOX Fuel Technology and MOX Performance in Germany; Plutonium Handling Experience -- 23. MOX in France: Domestic Programme and MELOX Plant -- 24. Experience on Development and Production of Vibropac MOX Fuel for Fast Reactors -- 25. Thermal and Fast MOX-Fuel from One Plant Advantages and Limitations -- 5: Summary of Workshop Presentations -- 6: NATO Workshop Summary Evaluation.
Record Nr. STANFORD-a10494938
[NATO Advanced Research Workshop on Mixed Oxide Fuel (Mox) Exploitation and Destruction in Power Reactors (1994 : Obninsk, Russia)]  
Materiale a stampa
Lo trovi qui: Stanford University
Thermal conductivity of uranium dioxide. Report of the panel held in Vienna, 26-30 April, 1965
Thermal conductivity of uranium dioxide. Report of the panel held in Vienna, 26-30 April, 1965
Creatore [Panel on Thermal Conductivity of Uranium Dioxide (1965 : Vienna, Austria)]
Estensione 68 p. illus. 24 cm.
Disciplina 621.48335
Accesso ente International Atomic Energy Agency
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. NYU-001919619
[Panel on Thermal Conductivity of Uranium Dioxide (1965 : Vienna, Austria)]  
Materiale a stampa
Lo trovi qui: New York University
Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment / edited by Kenneth L. Nash, Gregg J. Lumetta
Advanced separation techniques for nuclear fuel reprocessing and radioactive waste treatment / edited by Kenneth L. Nash, Gregg J. Lumetta
Estensione 1 online resource (xx, 492 pages) : illustrations.
Disciplina 621.48335
Accesso persona Nash, Kenneth L.
Lumetta, Gregg J., 1960-
Genere/Forma Electronic books
ISBN 9780857092274
0857092278
9781845695019
1845695011
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Nota di contenuto Chemistry of radioactive materials in the nuclear fuel cycle / K.L. Nash and J.C. Braley, Washington Sate University -- Physical and chemical properties of actinides in nuclear fuel reprocessing / A. Paulenova, Oregon State University -- Chemical engineering for advanced aqueous radioactive material separations / S. Arm and C. Phillips, EnergySolutions, LLC -- Spectroscopic on-line monitoring for process control and safeguarding of radiochemical streams in nuclear fuel reprocessing facilities / S.A. Bryan, T.G. Levitskaia, A.J. Casella, J.M. Peterson, A.M. Johnsen, A.M. Lines, and E.M. Thomas, Pacific Northwest National Laboratory -- Safeguards technology for radioactive materials processing and nuclear fuel reprocessing facilities / K.M. Goff, G.L. Frederickson and D.E. Vaden, Idaho National Laboratory -- Standard and advanced separation: PUREX processes for nuclear fuel reprocessing / R.S. Herbst, Idaho National Laboratory, P. Baron, CEA, France and M. Nilsson, University of California Irvine -- Alternative separation and extraction: UREX+ processes for actinide and targeted fission product recovery / M.C. Regalbuto, Argonne National Laboratory -- Advanced reprocessing for fission product separation and extraction / E.D. Collins, G.D. Del Cul, and B.A. Moyer, Oak Ridge National Laboratory -- Combined processes for high level radioactive waste separations: UNEX and other extraction processes / V.N. Romanovsky, I.V. Smirnov, V.A. Baabain and A. Yu Shadrin, Khlopin Radium Institute, Russia -- Nuclear engineering for pyrochemical treatment of spent nuclear fuels / T. Koyama, Central Research Institute of Electric Power Industry, Japan -- Development of highly selective compounds for solvent extraction processes: partitioning and transmutations of long-lived radionuclides from spent nuclear fuels / C. Hill, CEA, France -- Developments in the partitioning and transmutation of radioactive waste / D.M. Warin, CEA/Marcoule, France -- Solid-phase extraction technology for actinide and lanthanide separations in nuclear fuel reprocessing / T.J. Tranter, Idaho National Laboratory -- Emerging separation techniques: supercritical fluid and ionic liquid extraction techniques for nuclear fuel reprocessing and radioactive waste treatment / C.M. Wai, University of Idaho -- Development of biological treatment processes for the separation and recovery of radioactive wastes / E.M.N. Chirwa, University of Pretoria, South Africa.
Record Nr. NYU-005039890
Materiale a stampa
Lo trovi qui: New York University
The thermal conductivity of irradiated and unirradiated beryllia / by R.C. McGill, J.A.G. Smith
The thermal conductivity of irradiated and unirradiated beryllia / by R.C. McGill, J.A.G. Smith
Creatore [Atomic Energy Research Establishment (Harwell, England)]
Estensione 2 p. : ill. ; 28 cm.
Disciplina 621.48335
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. YALE-8964098
[Atomic Energy Research Establishment (Harwell, England)]  
Materiale a stampa
Lo trovi qui: Yale University
Laser isotope separation in atomic vapor / P.A. Bokhan ... [et al.].
Laser isotope separation in atomic vapor / P.A. Bokhan ... [et al.].
Estensione xiii, 185 p. : fig. (some col.), tab. ; 25 cm.
Disciplina 621.48335
Accesso persona Bokhan, P. A.
ISBN 3527406212 (hd.bd.)
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. YALE-7698968
Materiale a stampa
Lo trovi qui: Yale University
Zirconium in the nuclear industry [electronic resource] : tenth international symposium / Anand M. Garde and E. Ross Bradley, editors
Zirconium in the nuclear industry [electronic resource] : tenth international symposium / Anand M. Garde and E. Ross Bradley, editors
Estensione 1 online resource.
Disciplina 621.48335
Accesso persona Garde, A. M.
Bradley, E. R.
Accesso ente ASTM International
Accesso convegno International Symposium on Zirconium in the Nuclear Industry (10th : 1993 : Baltimore, Md.)
ISBN 9780803152861
0803152868
Formato Materiale a stampa
Livello bibliografico Monografia
Lingua di pubblicazione eng
Record Nr. UALBERTA-6616003
Materiale a stampa
Lo trovi qui: University of Alberta / NEOS Library Consortium