Explore: Liquid Metal Cooled Reactors

“Performance measurement system” Metadata:

• Title: Performance measurement system
• Author: ➤  United States. Dept. of Energy. Division of Reactor Research and Technology
• Language: English
• Number of Pages: Median: 69
• Publisher: ➤  Dept. of Energy, Assistant Secretary for Energy Technology, Division of Reactor Research and Technology - for sale by the National Technical Information Service
• Publish Date: 1978
• Publish Location: Springfield, Va - Washington

“Performance measurement system” Subjects and Themes:

• Subjects: Breeder reactors - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: ➤  OL14184082M - OL14862346M - OL14862356M - OL14862344M - OL14862347M - OL14862349M - OL14862351M

“Plane-strain stress intensity factors for cracked hexagonal subassembly ducts” Metadata:

• Title: ➤  Plane-strain stress intensity factors for cracked hexagonal subassembly ducts
• Author: Henry Petroski
• Language: English
• Number of Pages: Median: 43
• Publisher: ➤  for sale by the National Technical Information Service] - Dept. of Energy, Argonne National Laboratory
• Publish Date: 1977
• Publish Location: ➤  [Springfield, Va - Argonne, Ill

“Plane-strain stress intensity factors for cracked hexagonal subassembly ducts” Subjects and Themes:

• Subjects: ➤  Liquid metal cooled reactors - Corrosion - Effect of radiation on - Metals - Steel, Stainless - Stainless Steel

Edition Identifiers:

• The Open Library ID: OL17962884M - OL14863016M - OL15236778M - OL18016217M

“Comments on LMFBR cost-benefit analysis” Metadata:

• Title: ➤  Comments on LMFBR cost-benefit analysis
• Author: Arthur J. Alexander
• Language: English
• Number of Pages: Median: 18
• Publisher: Rand Corporation]
• Publish Date: 1975
• Publish Location: [Santa Monica

“Comments on LMFBR cost-benefit analysis” Subjects and Themes:

• Subjects: Breeder reactors - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL22394902M - OL16462914M

“Status of Liquid Metal Cooled Fast Breeder Reactors/Idc246 (Technical Reports Series (International Atomic Energy Agency))” Metadata:

• Title: ➤  Status of Liquid Metal Cooled Fast Breeder Reactors/Idc246 (Technical Reports Series (International Atomic Energy Agency))
• Author: ➤  International Atomic Energy Agency.
• Language: English
• Number of Pages: Median: 677
• Publisher: ➤  Intl Atomic Energy Agency - International Atomic Energy Agency
• Publish Date: 1985
• Publish Location: Vienna

“Status of Liquid Metal Cooled Fast Breeder Reactors/Idc246 (Technical Reports Series (International Atomic Energy Agency))” Subjects and Themes:

• Subjects: ➤  Nuclear reactors - Liquid metal cooled reactors - Liquid metal fast breeder reactors

Edition Identifiers:

• The Open Library ID: OL12892029M - OL17913148M
• All ISBNs: 9789201551856 - 9201551851

“Coupled hydrodynamic-structural response analysis of piping systems” Metadata:

• Title: ➤  Coupled hydrodynamic-structural response analysis of piping systems
• Author: M. T. A-Moneim
• Language: English
• Number of Pages: Median: 88
• Publisher: ➤  for sale by the Dept. of Energy, Technical Information Center - Dept. of Energy, [Office of Energy Research], Argonne National Laboratory
• Publish Date: 1978
• Publish Location: Oak Ridge, Tenn - Argonne, Ill

“Coupled hydrodynamic-structural response analysis of piping systems” Subjects and Themes:

• Subjects: Pipe - Liquid metal cooled reactors - Pipelines - Hydrodynamics

Edition Identifiers:

• The Open Library ID: OL18015104M - OL17649225M

“Coupled hydrodynamic-structural response analysis of piping systems” Metadata:

• Title: ➤  Coupled hydrodynamic-structural response analysis of piping systems
• Author: M. T A-Moneim
• Language: English
• Number of Pages: Median: 88
• Publisher: ➤  Dept. of Energy, [Office of Energy Research], Argonne National Laboratory - for sale by the Dept. of Energy, Technical Information Center
• Publish Date: 1978
• Publish Location: Argonne, Ill - Oak Ridge, Tenn

“Coupled hydrodynamic-structural response analysis of piping systems” Subjects and Themes:

• Subjects: Pipe - Liquid metal cooled reactors - Pipelines - Hydrodynamics

Edition Identifiers:

• The Open Library ID: OL17962888M - OL14863032M

“Multichannel clad-relocation model for fast-reactor loss-of-flow accidents” Metadata:

• Title: ➤  Multichannel clad-relocation model for fast-reactor loss-of-flow accidents
• Author: M Ishii
• Language: English
• Number of Pages: Median: 51
• Publisher: ➤  Dept. of Energy, [Office of Energy Research], Argonne National Laboratory - for sale by the National Technical Information Service]
• Publish Date: 1979
• Publish Location: ➤  [Springfield, Va - Argonne, Ill

“Multichannel clad-relocation model for fast-reactor loss-of-flow accidents” Subjects and Themes:

• Subjects: Safety measures - Liquid metal cooled reactors - Metal cladding

Edition Identifiers:

• The Open Library ID: OL17962966M - OL14863136M

“Survey of suppression of sodium fires in liquid metal fast breeder reactors” Metadata:

• Title: ➤  Survey of suppression of sodium fires in liquid metal fast breeder reactors
• Author: Russell A Hemstreet
• Language: English
• Number of Pages: Median: 18
• Publisher: ➤  for sale by the National Technical Information Service - U.S. Energy Research and Development Administration
• Publish Date: 1976
• Publish Location: Washington - Springfield, Va

“Survey of suppression of sodium fires in liquid metal fast breeder reactors” Subjects and Themes:

• Subjects: Breeder reactors - Safety measures - Liquid metal cooled reactors - Liquid sodium - Fire prevention

Edition Identifiers:

• The Open Library ID: OL14894672M - OL17968655M

“Performance measurement system : surveillance guide” Metadata:

• Title: ➤  Performance measurement system : surveillance guide
• Author: ➤  United States. Dept. of Energy. Division of Reactor Research and Technology.
• Language: English
• Number of Pages: Median: 55
• Publisher: ➤  Dept. of Energy, Assistant Secretary for Energy Technology, Division of Reactor Research and Technology - for sale by the National Technical Information Service
• Publish Date: 1978
• Publish Location: Washington - Springfield, Va

“Performance measurement system : surveillance guide” Subjects and Themes:

• Subjects: Breeder reactors - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL15223840M

“Multichannel clad-relocation model for fast-reactor loss-of-flow accidents” Metadata:

• Title: ➤  Multichannel clad-relocation model for fast-reactor loss-of-flow accidents
• Author: M. Ishii
• Language: English
• Number of Pages: Median: 51
• Publisher: ➤  Dept. of Energy, [Office of Energy Research], Argonne National Laboratory - for sale by the National Technical Information Service]
• Publish Date: 1979
• Publish Location: ➤  Argonne, Ill - [Springfield, Va

“Multichannel clad-relocation model for fast-reactor loss-of-flow accidents” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Metal cladding - Safety measures

Edition Identifiers:

• The Open Library ID: OL15236063M - OL18016028M

“Liquid metal reactors” Metadata:

• Title: Liquid metal reactors
• Author: ➤  United States. Congress. House. Committee on Energy and Commerce. Subcommittee on Energy and Power.
• Language: English
• Number of Pages: Median: 168
• Publisher: ➤  For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office - U.S. G.P.O.
• Publish Date: 1994
• Publish Location: Washington

“Liquid metal reactors” Subjects and Themes:

• Subjects: ➤  Economic aspects - Economic aspects of Nuclear power plants - Government policy - Liquid metal cooled reactors - Nuclear power plants - Nuclear reactors - Radioactive wastes - United States - United States. Dept. of Energy - United States. Department of Energy
• Places: United States

Edition Identifiers:

• The Open Library ID: OL17751654M - OL1195304M
• Online Computer Library Center (OCLC) ID: 30364189
• Library of Congress Control Number (LCCN): 94187399
• All ISBNs: 016044022X - 9780160440229

“Summary report (minutes of meetings)” Metadata:

• Title: ➤  Summary report (minutes of meetings)
• Author: ➤  Specialists' Meeting on Sodium-Water Reactions Melekess 1971.
• Language: English
• Number of Pages: Median: 261
• Publisher: ➤  U.S. Atomic Energy Commission, Office of Information Services; available from the National Technical Information Service, Springfield, Va.
• Publish Date: 1972
• Publish Location: [Washington

“Summary report (minutes of meetings)” Subjects and Themes:

• Subjects: Congresses - Liquid metal cooled reactors - Sodium-water reaction - Steam-boilers

Edition Identifiers:

• The Open Library ID: OL5392108M
• Library of Congress Control Number (LCCN): 72603661

“Multidisciplinary Design Approach and Safety Analysis of ADSR Cooled by Buoyancy Driven Flows” Metadata:

• Title: ➤  Multidisciplinary Design Approach and Safety Analysis of ADSR Cooled by Buoyancy Driven Flows
• Author: ➤  Carlos Alberto Ceballos Castillo
• Language: English
• Number of Pages: Median: 144
• Publisher: IOS Press
• Publish Date: 2007

“Multidisciplinary Design Approach and Safety Analysis of ADSR Cooled by Buoyancy Driven Flows” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Design and construction - Safety measures - Reactor fuel reprocessing

Edition Identifiers:

• The Open Library ID: OL12317760M
• Library of Congress Control Number (LCCN): 2007276538
• All ISBNs: 158603720X - 9781586037208

“Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic” Metadata:

• Title: ➤  Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic
• Author: IAEA
• Language: English
• Publisher: ➤  International Atomic Energy Agency
• Publish Date: 2012

“Liquid Metal Coolants for Fast Reactors Cooled by Sodium, Lead and Lead-Bismuth Eutectic” Subjects and Themes:

• Subjects: ➤  Liquid metal cooled reactors - Réacteurs à réfrigérant liquide métallique

Edition Identifiers:

• The Open Library ID: OL37157355M
• Online Computer Library Center (OCLC) ID: 843033019
• All ISBNs: 9789201318107 - 9201318103

“Status of Fast Reactor Research and Technology Development” Metadata:

• Title: ➤  Status of Fast Reactor Research and Technology Development
• Author: IAEA
• Language: English
• Publisher: ➤  International Atomic Energy Agency
• Publish Date: 2013

“Status of Fast Reactor Research and Technology Development” Subjects and Themes:

• Subjects: ➤  Fast reactors - Technological innovations - Cores - Sodium cooled reactors - Liquid metal cooled reactors - Gas cooled reactors - Réacteurs rapides - Innovations - Cœurs - Réacteurs refroidis au sodium - Réacteurs à réfrigérant liquide métallique - Réacteurs à réfrigérant gazeux

Edition Identifiers:

• The Open Library ID: OL37161881M
• Online Computer Library Center (OCLC) ID: 856530587
• All ISBNs: 9201306105 - 9789201306104

“Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors” Metadata:

• Title: ➤  Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors
• Author: IAEA
• Language: English
• Publisher: ➤  International Atomic Energy Agency
• Publish Date: 2013

“Challenges Related to the Use of Liquid Metal and Molten Salt Coolants in Advanced Reactors” Subjects and Themes:

• Subjects: ➤  Nuclear reactors - Cooling - Liquid metal cooled reactors - Research - Molten salt reactors - Réacteurs nucléaires - Refroidissement - Réacteurs à réfrigérant liquide métallique - Recherche - Réacteurs à sels fondus

Edition Identifiers:

• The Open Library ID: OL37168026M
• Online Computer Library Center (OCLC) ID: 863221451
• All ISBNs: 9789201399106 - 9201399103

“Proceedings” Metadata:

• Title: Proceedings
• Author: ➤  International Conference on Reliable Fuels for Liquid Metal Reactors (1986 Tucson, Ariz.)
• Language: English
• Number of Pages: Median: 825
• Publisher: ANS
• Publish Date: 1986
• Publish Location: La Grange Park, Ill., USA

“Proceedings” Subjects and Themes:

• Subjects: Congresses - Liquid metal cooled reactors - Nuclear fuels

Edition Identifiers:

• The Open Library ID: OL2484387M
• Library of Congress Control Number (LCCN): 87404985
• All ISBNs: 0894481266 - 9780894481260

“Teplo- i massoobmen v atomnykh ėnergeticheskikh ustanovkakh s reaktorami, okhlazhdaemymi zhidkimi metallami” Metadata:

• Title: ➤  Teplo- i massoobmen v atomnykh ėnergeticheskikh ustanovkakh s reaktorami, okhlazhdaemymi zhidkimi metallami
• Author: E. I. Nevstrueva
• Language: rus
• Number of Pages: Median: 91
• Publisher: ➤  Vses. in-t nauch. i tekhn. informat͡s︡ii
• Publish Date: 1982
• Publish Location: Moskva

“Teplo- i massoobmen v atomnykh ėnergeticheskikh ustanovkakh s reaktorami, okhlazhdaemymi zhidkimi metallami” Subjects and Themes:

• Subjects: Cooling - Heat - Liquid metal cooled reactors - Mass transfer - Transmission

Edition Identifiers:

• The Open Library ID: OL3203631M
• Online Computer Library Center (OCLC) ID: 10711762
• Library of Congress Control Number (LCCN): 83108607

“Sıvı soğutmalı bir nükleer reaktörün dinamik olaylar karşısındaki, davranış analizi” Metadata:

• Title: ➤  Sıvı soğutmalı bir nükleer reaktörün dinamik olaylar karşısındaki, davranış analizi
• Author: Ayşe Çataklı
• Language: tur
• Number of Pages: Median: 146
• Publisher: ➤  İ.T.Ü. Nükleer Enerji Enstitüsü
• Publish Date: 1980
• Publish Location: İstanbul]

“Sıvı soğutmalı bir nükleer reaktörün dinamik olaylar karşısındaki, davranış analizi” Subjects and Themes:

• Subjects: ➤  Nuclear fuel rods - Protection - Data processing - Mathematical models - Liquid metal cooled reactors - Thermal properties

Edition Identifiers:

• The Open Library ID: OL30131912M
• Library of Congress Control Number (LCCN): 00389857

“Liquid-metal heat transfer and fluid dynamics” Metadata:

• Title: ➤  Liquid-metal heat transfer and fluid dynamics
• Language: English
• Number of Pages: Median: 179
• Publisher: ➤  American Society of Mechanical Engineers
• Publish Date: 1970
• Publish Location: New York

“Liquid-metal heat transfer and fluid dynamics” Subjects and Themes:

• Subjects: ➤  Heat - Congresses - Liquid metals - Transmission - Liquid metal cooled reactors - Thermal properties

Edition Identifiers:

• The Open Library ID: OL4914821M
• Library of Congress Control Number (LCCN): 76141816

“Phénix, prototypes fast-neutron nuclear power station” Metadata:

• Title: ➤  Phénix, prototypes fast-neutron nuclear power station
• Author: ➤  France. Commissariat à l'énergie atomique
• Language: English
• Number of Pages: Median: 217
• Publisher: ➤  U.S. Atomic Energy Commission, Division of Technical Information; [available from the Clearinghouse for Federal Scientific and Technical Information, Springfield, Va.
• Publish Date: 1970
• Publish Location: [Oak Ridge, Tenn.]

“Phénix, prototypes fast-neutron nuclear power station” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Nuclear power plants

Edition Identifiers:

• The Open Library ID: OL4854784M
• Library of Congress Control Number (LCCN): 75607198

“Zhidkometallicheskie teplonositeli I︠A︡ĖU” Metadata:

• Title: ➤  Zhidkometallicheskie teplonositeli I︠A︡ĖU
• Language: rus
• Number of Pages: Median: 125
• Publisher: Ėnergoatomizdat
• Publish Date: 1983
• Publish Location: Moskva

“Zhidkometallicheskie teplonositeli I︠A︡ĖU” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Liquid metals

Edition Identifiers:

• The Open Library ID: OL2903626M
• Library of Congress Control Number (LCCN): 84132434

“Sodium-cooled fast reactor engineering” Metadata:

• Title: ➤  Sodium-cooled fast reactor engineering
• Author: ➤  Symposium on Progress in Sodium-Cooled Fast Reactor Engineering, Monaco 1970
• Language: English
• Number of Pages: Median: 957
• Publisher: ➤  International Atomic Energy Agency
• Publish Date: 1970
• Publish Location: Vienna

“Sodium-cooled fast reactor engineering” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Congresses

Edition Identifiers:

• The Open Library ID: OL17420539M

“MgO insulated coaxial instrument cable development for FFTF in-vessel temperature and voltage conditions” Metadata:

• Title: ➤  MgO insulated coaxial instrument cable development for FFTF in-vessel temperature and voltage conditions
• Author: A. I. Y Chan
• Language: English
• Number of Pages: Median: 26
• Publisher: ➤  Dept. of Energy, Hanford Engineering Development Laboratory - for sale by the National Technical Information Service
• Publish Date: 1978
• Publish Location: ➤  Springfield, Va - Richland, Wash

“MgO insulated coaxial instrument cable development for FFTF in-vessel temperature and voltage conditions” Subjects and Themes:

• Subjects: Electronic instruments - Liquid metal cooled reactors - Coaxial cables

Edition Identifiers:

• The Open Library ID: OL14879957M

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Metadata:

• Title: ➤  Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology
• Author: ➤  Oak Ridge National Laboratory. Engineering Physics Division.
• Language: English
• Number of Pages: Median: 22
• Publisher: ➤  for sale by the National Technical Information Service] - Dept. of Energy, Oak Ridge National Laboratory
• Publish Date: 1979
• Publish Location: ➤  [Springfield, Va - Oak Ridge, Tenn

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Subjects and Themes:

• Subjects: ➤  Cross sections (Nuclear physics) - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL17964430M

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Metadata:

• Title: ➤  Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology
• Author: ➤  Oak Ridge National Laboratory. Engineering Physics Division.
• Language: English
• Number of Pages: Median: 22
• Publisher: ➤  for sale by the National Technical Information Service] - Dept. of Energy, Oak Ridge National Laboratory
• Publish Date: 1979
• Publish Location: ➤  [Springfield, Va - Oak Ridge, Tenn

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Subjects and Themes:

• Subjects: ➤  Cross sections (Nuclear physics) - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL14881197M

“A study of the reactivity of bubble collapse in molten liquid metal cooled reactors” Metadata:

• Title: ➤  A study of the reactivity of bubble collapse in molten liquid metal cooled reactors
• Author: F J Munno
• Language: English
• Number of Pages: Median: 55
• Publisher: ➤  for sale by the National Technical Information Service - Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Project Management
• Publish Date: 1978
• Publish Location: Springfield, Va - [Washington]

“A study of the reactivity of bubble collapse in molten liquid metal cooled reactors” Subjects and Themes:

• Subjects: Bubbles - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL14947416M

“Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident” Metadata:

• Title: ➤  Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident
• Author: P L Gardner
• Language: English
• Number of Pages: Median: 141
• Publisher: ➤  Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Division of Reactor Safety Research - for sale by the National Technical Information Service
• Publish Date: 1977
• Publish Location: Springfield, Va - Washington

“Condensation of fuel onto the above-core structure during an LMFBR core-disruptive accident” Subjects and Themes:

• Subjects: Nuclear fuels - Liquid metal cooled reactors - Condensation - Breeder reactors - Nuclear reactor accidents

Edition Identifiers:

• The Open Library ID: OL14947466M

“A corrosion critique of the 2 1/4 Cr-1 Mo steel for LMFBR steam generation system applications” Metadata:

• Title: ➤  A corrosion critique of the 2 1/4 Cr-1 Mo steel for LMFBR steam generation system applications
• Author: G. E Zima
• Language: English
• Number of Pages: Median: 73
• Publisher: ➤  Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Division of Systems Safety - for sale by the National Technical Information Service
• Publish Date: 1977
• Publish Location: Springfield, Va - Washington

“A corrosion critique of the 2 1/4 Cr-1 Mo steel for LMFBR steam generation system applications” Subjects and Themes:

• Subjects: ➤  Steel - Corrosion - Breeder reactors - Steam power plants - Fast reactors - Liquid metal cooled reactors
• Places: United States

Edition Identifiers:

• The Open Library ID: OL14947490M

“The APRICOT program” Metadata:

• Title: The APRICOT program
• Author: Science Applications, inc
• Language: English
• Number of Pages: Median: 93
• Publisher: ➤  Dept. of Energy, Division of Reactor Research and Demonstration - for sale by the National Technical Information Service
• Publish Date: 1977
• Publish Location: Washington - Springfield, Va

“The APRICOT program” Subjects and Themes:

• Subjects: Mathematical models - Safety measures - Liquid metal cooled reactors - Breeder reactors

Edition Identifiers:

• The Open Library ID: OL14882701M
• Online Computer Library Center (OCLC) ID: 3798418

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Metadata:

• Title: ➤  Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology
• Author: ➤  Oak Ridge National Laboratory. Engineering Physics Division.
• Language: English
• Number of Pages: Median: 22
• Publisher: ➤  for sale by the National Technical Information Service] - Dept. of Energy, Oak Ridge National Laboratory
• Publish Date: 1979
• Publish Location: ➤  Oak Ridge, Tenn - [Springfield, Va

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Subjects and Themes:

• Subjects: ➤  Cross sections (Nuclear physics) - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL18016315M

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Metadata:

• Title: ➤  Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology
• Author: ➤  Oak Ridge National Laboratory. Engineering Physics Division.
• Language: English
• Number of Pages: Median: 22
• Publisher: ➤  for sale by the National Technical Information Service] - Dept. of Energy, Oak Ridge National Laboratory
• Publish Date: 1979
• Publish Location: ➤  Oak Ridge, Tenn - [Springfield, Va

“Vitamin-E, an ENDF/B-V multigroup cross section library for LMFBR core and shield, LWR shield, dosimetry and fusion blanket technology” Subjects and Themes:

• Subjects: ➤  Cross sections (Nuclear physics) - Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL15237014M

“Proceedings of the International Conference on Liquid Metal Technology in Energy Production, ... May 3-6, 1976, Champion, Pennsylvania” Metadata:

• Title: ➤  Proceedings of the International Conference on Liquid Metal Technology in Energy Production, ... May 3-6, 1976, Champion, Pennsylvania
• Author: ➤  International Conference on Liquid Metal Technology in Energy Production Champion, Pa. 1976.
• Language: English
• Number of Pages: Median: 451
• Publisher: ➤  Energy Research and Development Administration - for sale by the National Technical Information Service
• Publish Date: 1976
• Publish Location: [Washington] - Springfield, Va

“Proceedings of the International Conference on Liquid Metal Technology in Energy Production, ... May 3-6, 1976, Champion, Pennsylvania” Subjects and Themes:

• Subjects: Liquid metal cooled reactors

Edition Identifiers:

• The Open Library ID: OL22440744M

“Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor” Metadata:

• Title: ➤  Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor
• Language: English
• Publisher: ➤  Supt. of Docs., U.S. G.P.O. [distributor] - Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission
• Publish Date: 1994
• Publish Location: Washington, DC

“Preapplication safety evaluation report for the power reactor innovative small module (PRISM) liquid-metal reactor” Subjects and Themes:

• Subjects: Evaluation - Safety measures - Liquid metal cooled reactors - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL14450707M
• Online Computer Library Center (OCLC) ID: 30823861

“Lithium-boiling potassium test loop” Metadata:

• Title: ➤  Lithium-boiling potassium test loop
• Author: ➤  California Institute of Technology, Pasadena. Jet Propulsion Laboratory
• Language: English
• Number of Pages: Median: 62
• Publish Date: 1966
• Publish Location: Pasadena

“Lithium-boiling potassium test loop” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Lithium - Potassium

Edition Identifiers:

• The Open Library ID: OL5293933M
• Library of Congress Control Number (LCCN): 72016933

“Review of the liquid metal fast breeder reactor program” Metadata:

• Title: ➤  Review of the liquid metal fast breeder reactor program
• Author: ➤  United States. Congress. Joint Committee on Atomic Energy. Ad Hoc Subcommittee to Review the Liquid Metal Fast Breeder Reactor Program.
• Language: English
• Number of Pages: Median: 1150
• Publisher: U.S. Govt. Print. Off.
• Publish Date: 1975
• Publish Location: Washington

“Review of the liquid metal fast breeder reactor program” Subjects and Themes:

• Subjects: Breeder reactors - Liquid metal cooled reactors - Nuclear engineering
• Places: United States

Edition Identifiers:

• The Open Library ID: OL5014905M
• Library of Congress Control Number (LCCN): 76602518

“Bezopasnostʹ raboty s litiem, natriem, kaliem” Metadata:

• Title: ➤  Bezopasnostʹ raboty s litiem, natriem, kaliem
• Author: Mikhail Andreevich Gorokhov
• Language: rus
• Number of Pages: Median: 176
• Publisher: Atomizdat
• Publish Date: 1971
• Publish Location: Moskva

“Bezopasnostʹ raboty s litiem, natriem, kaliem” Subjects and Themes:

• Subjects: Alkali metals - Liquid metal cooled reactors - Radioactivity - Safety measures

Edition Identifiers:

• The Open Library ID: OL5358076M
• Online Computer Library Center (OCLC) ID: 3827091
• Library of Congress Control Number (LCCN): 72317012

“Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors” Metadata:

• Title: ➤  Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors
• Author: ➤  Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors (3rd 1976 Tokyo, Japan)
• Language: English
• Publisher: ➤  Power Reactor and Nuclear Fuel Development Corp.
• Publish Date: 1976
• Publish Location: [Tokyo]

“Proceedings of the Third Specialist Meeting on Sodium/Fuel Interaction in Fast Reactors” Subjects and Themes:

• Subjects: Congresses - Fast reactors - Liquid metal cooled reactors - Liquid sodium - Nuclear fuels

Edition Identifiers:

• The Open Library ID: OL4614649M
• Library of Congress Control Number (LCCN): 77378662

“Liquid metal fast breeder reactor program” Metadata:

• Title: ➤  Liquid metal fast breeder reactor program
• Author: ➤  United States. Energy Research and Development Administration.
• Language: English
• Publisher: ➤  The Administration : for sale by the Supt. of Docs., U.S. Govt. Print. Off.
• Publish Date: 1975
• Publish Location: Washington

“Liquid metal fast breeder reactor program” Subjects and Themes:

• Subjects: Breeder reactors - Liquid metal cooled reactors - Nuclear engineering
• Places: United States

Edition Identifiers:

• The Open Library ID: OL5013664M
• Online Computer Library Center (OCLC) ID: 2819702
• Library of Congress Control Number (LCCN): 76601156

“Department of Energy's actinide recycle and liquid metal reactor programs” Metadata:

• Title: ➤  Department of Energy's actinide recycle and liquid metal reactor programs
• Author: ➤  United States. Congress. Senate. Committee on Energy and Natural Resources.
• Language: English
• Number of Pages: Median: 132
• Publisher: ➤  U.S. G.P.O. - For sale by the U.S. G.P.O., Supt. of Docs., Congressional Sales Office
• Publish Date: 1993
• Publish Location: Washington

“Department of Energy's actinide recycle and liquid metal reactor programs” Subjects and Themes:

• Subjects: ➤  United States - Recycling - Liquid metal cooled reactors - United States. Dept. of Energy - Actinide elements - United States. Department of Energy

Edition Identifiers:

• The Open Library ID: OL1161974M
• Online Computer Library Center (OCLC) ID: 29173016
• Library of Congress Control Number (LCCN): 94141089
• All ISBNs: 9780160415104 - 0160415101

“Opredelenie temperatury v tvėlakh i︠a︡dernogo reaktora” Metadata:

• Title: ➤  Opredelenie temperatury v tvėlakh i︠a︡dernogo reaktora
• Language: rus
• Number of Pages: Median: 228
• Publisher: Atomizdat
• Publish Date: 1978
• Publish Location: Moskva

“Opredelenie temperatury v tvėlakh i︠a︡dernogo reaktora” Subjects and Themes:

• Subjects: Nuclear fuel elements - Liquid metal cooled reactors - Thermal properties

Edition Identifiers:

• The Open Library ID: OL3850727M
• Library of Congress Control Number (LCCN): 81168647

“Avariĭnye i perekhodnye prot͡sessy v bystrykh reaktorakh” Metadata:

• Title: ➤  Avariĭnye i perekhodnye prot͡sessy v bystrykh reaktorakh
• Author: I. A. Kuznet͡sov
• Language: rus
• Number of Pages: Median: 171
• Publisher: Ėnergoatomizdat
• Publish Date: 1987
• Publish Location: Moskva

“Avariĭnye i perekhodnye prot͡sessy v bystrykh reaktorakh” Subjects and Themes:

• Subjects: Fast reactors - Liquid metal cooled reactors - Safety measures

Edition Identifiers:

• The Open Library ID: OL2324072M
• Online Computer Library Center (OCLC) ID: 18020667
• Library of Congress Control Number (LCCN): 86208412

“Proceedings of the second Fusion-Fission Energy Systems Review Meeting, November 2 and 3, 1977, Washington, D.C” Metadata:

• Title: ➤  Proceedings of the second Fusion-Fission Energy Systems Review Meeting, November 2 and 3, 1977, Washington, D.C
• Author: ➤  Fusion-Fission Energy Systems Review Meeting (2nd 1977 Washington, D.C.)
• Language: English
• Publisher: ➤  Dept. of Energy, Assistant Secretary for Energy Technology, Office of Fusion Energy : for sale by the Supt. of Docs., U.S. Govt. Print. Off.
• Publish Date: 1978
• Publish Location: Washington

“Proceedings of the second Fusion-Fission Energy Systems Review Meeting, November 2 and 3, 1977, Washington, D.C” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Uranium

Edition Identifiers:

• The Open Library ID: OL17638117M
• Online Computer Library Center (OCLC) ID: 4173381

“Zhidkometallicheskie teplonositeli I︠A︡ĖU” Metadata:

• Title: ➤  Zhidkometallicheskie teplonositeli I︠A︡ĖU

“Zhidkometallicheskie teplonositeli I︠A︡ĖU” Subjects and Themes:

• Subjects: Liquid metal cooled reactors - Liquid metals