Recycling of plutonium and uranium in water reactor fuel :...

Main
Recycling of plutonium and uranium in...

Recycling of plutonium and uranium in water reactor fuel : proceedings of a Technical Committee meeting held in Newby Bridge, Windermere, United Kingdom, 3-7 July 1995

International Atomic Energy Agency. Technical Committee on Recycling of Plutonium and Uranium in Water Reactor Fuel

0 / 0

Jak bardzo podobała Ci się ta książka?

Jaka jest jakość pobranego pliku?

Pobierz książkę, aby ocenić jej jakość

Jaka jest jakość pobranych plików?

Rok:

1997

Wydawnictwo:

IAEA

Język:

english

Strony:

370

Serie:

IAEA-TECDOC, 941

Plik:

PDF, 24.99 MB

IPFS:

,

english, 1997

Czytaj Online

Trwa konwersja do

Konwersja do nie powiodła się

Możesz być zainteresowany

— Separation and Extraction of Plutonium in Mixed Waste

R A Roberts; Inc St Louis MO (USA) Medical Products R and D Mallinckrodt; Tallahassee (USA) Dept of Chemistry Florida State Univ; CA Lawrence Livermore National Lab (USA); G R Choppin; All authors — Radiochemistry of uranium, neptunium and plutonium: an updating

William T. Carnall and Gregory R. Choppin (Eds.) — Plutonium Chemistry

Organisation for Economic Co-Operation and Development — Physics of Plutonium Recycling: Bwr Mox Benchmark - Specifications and Results (Nuclear Science)

— Pu Consumption in Advanced Light Water Reactors

— Status and Trends in Spent Fuel Reprocessing (IAEA TECDOC-1103)

— Studies on Fuels with Low Fission Gas Release (IAEA TECDOC-970)

— Adv Fuel Pellet Mtls, Designs for Water-Cooled Reactors (IAEA TECDOC-1416)

— Adv in Fuel-Pellet Tech for Imprvd Perf at High Burnup (IAEA TECDOC-1036)

— Advanced Fuels with Reduced Actinide Generation (IAEA TECDOC-0916)

— Advanced Post-Irradiation Exam Tech for Water-Reactor Fuel (IAEA TECDOC-1277)

— Eval of LWR Spent Fuel Composition Data

— Fission Gas Release, Fuel Rod Chem Related to Extended Burnup (IAEA TECDOC-697)

— Fuel Safety Criteria - Tech Review (csni-r99-25)

— Nuclear Fuel Behavior Modelling at High Burnup (and exper support) (IAEA TECDOC-1233)

— Proceedings of Topical Meeting on RIA Vol 2 (csni-r2003-8-vol2)

— Review of Tech Issues Related to Burnup Credit for LWR Fuel

— Scientific Issues in (nuclear) Fuel Behavior (NEA 0213)

— Spent Fuel Management - Status, Prospects (IAEA TECDOC-1006)

— Transient Behavior of High-Burnup Fuel (csni-r1996-23)

— Transient Behavior of High-Burnup Fuel (csni-r95-22)

— Use of Recycle Pu in Mixed-Oxide Fuel [LWRs] Vol 1 (summary)

— Water Reactor Fuel Element Modeling at High Burnup (IAEA TECDOC-0957)

— Zircalloy Clad [nuclear] Fuel Analysis

International Atomic Energy Agency — Fuel failure in normal operation of water reactors : experience, mechanisms and management : proceedings of a Technical Committee meeting held in Dimitrovgrad, Russian Federation, 26-29 May 1992

Broadhead, B.L.; Oak Ridge National Laboratory.; United States. Dept. of Energy. Assistant Secretary for Human Resources and Administration.; United States. Dept. of Energy. Office of Scientific and Technical Information — K-infinite trends with burnup, enrichment, and cooling time for BWR fuel assemblies

International Atomic Energy Agency — Technical aspects of high converter reactors : proceedings of a Technical Committee meeting held in Nuremberg, 26-29 March 1990

Olsen, C.S.; Sterbentz, J.W.; Sinha, U.P.; USDOE, Washington, DC (United States);National Academy of Sciences, Washington, DC (United States); Idaho National Engineering Laboratory.; Idaho National Engineering and Environmental Laboratory.; United States. — Weapons-grade plutonium dispositioning. Volume 4. Plutonium dispositioning in light water reactors

International Atomic Energy Agency — Development status of metallic, dispersion and non-oxide advanced and alternative fuels for power and research reactors

— Role of thorium to supplement fuel cycles of future nuclear energy systems

Onoufriev V. (ред.) — Fuel failure in water reactors

— Research Reactor Fuel Management 1 (RRFM 1997)

— Research Reactor Fuel Management 4 (RRFM 2000)

OECD — Nuclear fuel safety criteria technical review

Brian R. T. Frost (Auth.) — Nuclear Fuel Elements. Design, Fabrication and Performance

R.J.M. Konings (editor) — Comprehensive Nuclear Materials, Volume 2: Material Properties / Oxide Fuels for Light Water Reactors and Fast Neutron Reactors

coll. — TopFuel'97 : proceedings of the conference organized by the British Nuclear Energy Society and held in Manchester on 9-11 June 1997

— The physics problems in thermal reactor design proceedings of an international conference at the Institution of Civil Engineers, London SWl, 27-29 June 1967

J. Walker, D. R. Weaver (auth.), Ernest J. Henley, Jeffery Lewins, Martin Becker (eds.) — Advances in Nuclear Science and Technology: Volume 11

Najbardziej popularne frazy