Design study of long-life small modular sodium-cooled fast reactor.
- Published in:
- International Journal of Energy Research, 2017, v. 41, n. 1, p. 139, doi. 10.1002/er.3609
- By:
- Publication type:
- Article
Works matching DE "SODIUM graphite reactors"
Results: 16
1
2
Major Activities in the U.S. Atomic Energy Program.
- Published in:
- Bulletin of the Atomic Scientists, 1954, v. 10, n. 9, p. 360, doi. 10.1080/00963402.1954.11453530
- Publication type:
- Article
3
Magnetic Flowmeter for Fast Sodium Reactors.
- Published in:
- Atomic Energy, 2017, v. 122, n. 4, p. 243, doi. 10.1007/s10512-017-0262-8
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- Publication type:
- Article
4
High-Priority R&D Problems of Advanced Fast Sodium Reactors.
- Published in:
- Atomic Energy, 2016, v. 121, n. 1, p. 10, doi. 10.1007/s10512-016-0155-2
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- Publication type:
- Article
5
Nitride Fuel for a Prospective BN-1200 Type Fast Sodium Reactor.
- Published in:
- Atomic Energy, 2013, v. 114, n. 5, p. 331, doi. 10.1007/s10512-013-9720-0
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- Publication type:
- Article
6
DEVELOPMENT AND APPLICATION OF AN INTEGRATED FUEL PERFORMANCE AND SUBCHANNEL MODEL FOR ANALYSIS OF SODIUM FAST REACTORS.
- Published in:
- Nuclear Technology, 2013, v. 184, n. 1, p. 63, doi. 10.13182/NT13-A19869
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- Publication type:
- Article
7
DEVELOPMENT OF PASSIVE SHUTDOWN SYSTEM FOR SFR.
- Published in:
- Nuclear Technology, 2010, v. 170, n. 1, p. 181, doi. 10.13182/NT10-A9456
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- Publication type:
- Article
8
MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR.
- Published in:
- Nuclear Technology, 2010, v. 170, n. 1, p. 170, doi. 10.13182/NT10-A9455
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- Publication type:
- Article
9
TECHNOLOGICAL FEASIBILITY OF TWO-LOOP COOLING SYSTEM IN JSFR.
- Published in:
- Nuclear Technology, 2010, v. 170, n. 1, p. 159, doi. 10.13182/NT09-6
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- Publication type:
- Article
10
Mass Transfer of Corrosion Products in the Nonisothermal Sodium Loop of a Fast Reactor.
- Published in:
- Journal of Engineering Physics & Thermophysics, 2014, v. 87, n. 6, p. 1532, doi. 10.1007/s10891-014-1159-1
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- Publication type:
- Article
11
Safety Design and Evaluation in a Large-Scale Japan Sodium-Cooled Fast Reactor.
- Published in:
- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/614973
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- Publication type:
- Article
12
Dynamic Analysis of a Pyroprocessing Coupled SFR Fuel Recycling.
- Published in:
- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/390758
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- Publication type:
- Article
13
Study on Detailed Calculation and Experiment Methods of Neutronics, Fuel Materials, and Thermal Hydraulics for a Commercial Type Japanese Sodium-Cooled Fast Reactor.
- Published in:
- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/351809
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- Publication type:
- Article
14
Economic Analysis of Different Nuclear Fuel Cycle Options.
- Published in:
- Science & Technology of Nuclear Installations, 2012, p. 1, doi. 10.1155/2012/293467
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- Publication type:
- Article
15
Ferritic steels for sodium-cooled fast reactors: Design principles and challenges.
- Published in:
- JOM: The Journal of The Minerals, Metals & Materials Society (TMS), 2010, v. 62, n. 9, p. 75, doi. 10.1007/s11837-010-0143-2
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- Publication type:
- Article
16
Analysis of features of hydrodynamics and heat transfer in the fuel assembly of prospective sodium reactor with a high rate of reproduction in the uranium-plutonium fuel cycle.
- Published in:
- Physics of Atomic Nuclei, 2016, v. 79, n. 8, p. 1315, doi. 10.1134/S1063778816080111
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- Publication type:
- Article