Explore: Sodium Cooled Reactors

“Reactivity coefficients in large fast power reactors” Metadata:

• Title: ➤  Reactivity coefficients in large fast power reactors
• Author: Harry H. Hummel
• Language: English
• Number of Pages: Median: 390
• Publisher: American Nuclear Society
• Publish Date: 1970 - 1978
• Publish Location: ➤  [Hinsdale, Ill.] - [La Grange Park, Ill.]

“Reactivity coefficients in large fast power reactors” Subjects and Themes:

• Subjects: Nuclear fuels - Nuclear reactors - Reactivity - Reactivity (Nuclear engineering) - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL5445754M - OL4550034M
• Online Computer Library Center (OCLC) ID: 88733
• Library of Congress Control Number (LCCN): 77018553 - 73119000
• All ISBNs: 0894480065 - 9780894480065

“Sodium Fast Reactors with Closed Fuel Cycle” Metadata:

• Title: ➤  Sodium Fast Reactors with Closed Fuel Cycle
• Authors: Baldev RajP. ChellapandiP. R. Vasudeva Rao
• Language: English
• Number of Pages: Median: 901
• Publisher: Taylor & Francis Group
• Publish Date: 2015 - 2017

“Sodium Fast Reactors with Closed Fuel Cycle” Subjects and Themes:

• Subjects: ➤  Nuclear reactors - Pulsed reactors - Sodium cooled reactors - Fast reactors - Réacteurs refroidis au sodium - Réacteurs rapides - TECHNOLOGY & ENGINEERING - Mechanical

Edition Identifiers:

• The Open Library ID: ➤  OL28764806M - OL33684680M - OL28857941M - OL33748257M - OL33700513M - OL33516187M
• Online Computer Library Center (OCLC) ID: 893631784
• All ISBNs: ➤  1466587679 - 0429167792 - 9781351231404 - 9781351230223 - 9781138893047 - 9781466587670 - 9781466587694 - 9780429167799 - 1138893048 - 1351231405 - 1466587695 - 1351230220

“Compatibility of different brazing alloys during long time exposure in sodium loop” Metadata:

• Title: ➤  Compatibility of different brazing alloys during long time exposure in sodium loop
• Author: M. Soenen
• Language: English
• Number of Pages: Median: 17
• Publisher: ➤  Centre d'étude de l'énergie nucléaire
• Publish Date: 1966
• Publish Location: Mol, Belgium

“Compatibility of different brazing alloys during long time exposure in sodium loop” Subjects and Themes:

• Subjects: Brazing alloys - Materials - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL3917092M
• Library of Congress Control Number (LCCN): 81483230

“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

“Bezopasnostʹ parogeneratorov natriĭ-voda” Metadata:

• Title: ➤  Bezopasnostʹ parogeneratorov natriĭ-voda
• Author: ➤  V. M. (Vladimir Mikhaĭlovich) Poplavskiĭ
• Language: rus
• Number of Pages: Median: 140
• Publisher: Ėnergoatomizdat
• Publish Date: 1990
• Publish Location: Moskva

“Bezopasnostʹ parogeneratorov natriĭ-voda” Subjects and Themes:

• Subjects: Fast reactors - Safety measures - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL1962208M
• Online Computer Library Center (OCLC) ID: 22451908
• Library of Congress Control Number (LCCN): 90193844
• All ISBNs: 5283037754 - 9785283037752

“Tekhnika raboty s natriem na AĖS” Metadata:

• Title: ➤  Tekhnika raboty s natriem na AĖS
• Author: V. M. Arkhipov
• Language: rus
• Number of Pages: Median: 134
• Publisher: Ėnergoatomizdat
• Publish Date: 1986
• Publish Location: Moskva

“Tekhnika raboty s natriem na AĖS” Subjects and Themes:

• Subjects: Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL2756120M
• Library of Congress Control Number (LCCN): 86109615

“Na gong yi ji chu” Metadata:

• Title: Na gong yi ji chu
• Author: Shunzhang Hong
• Language: chi
• Number of Pages: Median: 110
• Publisher: ➤  Zhongguo yuan zi neng chu ban chuan mei you xian gong si
• Publish Date: 2011
• Publish Location: Beijing Shi

“Na gong yi ji chu” Subjects and Themes:

• Subjects: Liquid sodium - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL30443215M
• Online Computer Library Center (OCLC) ID: 815359848
• Library of Congress Control Number (LCCN): 2012410993
• All ISBNs: 9787502251918 - 750225191X

“Optimisation of sodium-cooled fast reactors” Metadata:

• Title: ➤  Optimisation of sodium-cooled fast reactors
• Author: Joyce S. Davis
• Language: English
• Number of Pages: Median: 464
• Publisher: British Nuclear Energy Society
• Publish Date: 1978
• Publish Location: London

“Optimisation of sodium-cooled fast reactors” Subjects and Themes:

• Subjects: ➤  Fast reactors - Congresses - Nuclear power plants - Sodium cooled reactors - Pulsed reactors - Nuclear reactors

Edition Identifiers:

• The Open Library ID: OL4475348M
• Library of Congress Control Number (LCCN): 79302852
• All ISBNs: 9780727700544 - 0727700545

“Liquid metal thermal-hydraulics” Metadata:

• Title: ➤  Liquid metal thermal-hydraulics
• Language: English
• Number of Pages: Median: 397
• Publisher: Inforum Verlags
• Publish Date: 1994
• Publish Location: [Bonn]

“Liquid metal thermal-hydraulics” Subjects and Themes:

• Subjects: ➤  Heat - Computer simulation - Fluid dynamics - Liquid metal fast breeder reactors - Transmission - Nuclear reactors - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL719527M
• Library of Congress Control Number (LCCN): 97106013
• All ISBNs: 3926956224 - 9783926956224

“European sodium component testing facilities (report of September-October 1975 trip)” Metadata:

• Title: ➤  European sodium component testing facilities (report of September-October 1975 trip)
• Author: W. S Debear
• Language: English
• Number of Pages: Median: 116
• Publisher: ➤  Available from National Technical Information Service - U.S. Energy Research & Development Administration
• Publish Date: 1975
• Publish Location: Washington - Springfield, Va

“European sodium component testing facilities (report of September-October 1975 trip)” Subjects and Themes:

• Subjects: Nuclear power plants - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL15478140M

“Comparison of containment systems for large sodium-cooled breeder reactors” Metadata:

• Title: ➤  Comparison of containment systems for large sodium-cooled breeder reactors
• Author: S. E Seeman
• Language: English
• Number of Pages: Median: 197
• 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

“Comparison of containment systems for large sodium-cooled breeder reactors” Subjects and Themes:

• Subjects: Nuclear reactors - Breeder reactors - Sodium cooled reactors - Containment

Edition Identifiers:

• The Open Library ID: OL14879967M

“Sodium flow distribution in test fuel assembly P-23B” Metadata:

• Title: ➤  Sodium flow distribution in test fuel assembly P-23B
• Author: J. P. S Taylor
• Language: English
• Number of Pages: Median: 91
• 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

“Sodium flow distribution in test fuel assembly P-23B” Subjects and Themes:

• Subjects: Nuclear fuel claddings - Effect of radiation on - Sodium cooled reactors - Flow meters

Edition Identifiers:

• The Open Library ID: OL14879972M

“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

“Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh” Metadata:

• Title: ➤  Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh
• Language: rus
• Number of Pages: Median: 174
• Publisher: Atomizdat
• Publish Date: 1980
• Publish Location: Moskva

“Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh” Subjects and Themes:

• Subjects: Control - Safety measures - Fast reactors - Sodium cooled reactors

Edition Identifiers:

• The Open Library ID: OL4217017M
• Library of Congress Control Number (LCCN): 80496658

“Sodium-cooled fast reactor engineering” Metadata:

• Title: ➤  Sodium-cooled fast reactor engineering
• Author: ➤  Symposium on Progress in Sodium-Cooled Fast Reactor Engineering Monaco 1970.
• Languages: rus - 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: Breeder reactors - Congresses - Sodium cooled reactors - Nuclear Reactors

Edition Identifiers:

• The Open Library ID: OL4370740M
• Online Computer Library Center (OCLC) ID: 137591
• Library of Congress Control Number (LCCN): 78552748

“Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh” Metadata:

• Title: ➤  Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh

“Ispolnitelʹnye mekhanizmy organov upravlenii︠a︡ i zashchity dli︠a︡ natrievykh reaktorov na bystrykh neĭtronakh” Subjects and Themes:

• Subjects: Control - Safety measures - Fast reactors - Sodium cooled reactors