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Non-Free Swelling of Uranium Dioxide Fuel at Burnup 8-13% h.a.
- Published in:
- Atomic Energy, 2017, v. 121, n. 4, p. 249, doi. 10.1007/s10512-017-0192-5
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- Article
Equipment and Methods of Post-Reactor Studies of Materials in a Block of Shielded Enclosures at Institute of Reactor Materials.
- Published in:
- Atomic Energy, 2017, v. 121, n. 4, p. 240, doi. 10.1007/s10512-017-0191-6
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- Article
Dependence of the Electronic Thermal Conductivity of ChS-68 Steel on Radiation Swelling.
- Published in:
- Atomic Energy, 2017, v. 121, n. 4, p. 292, doi. 10.1007/s10512-017-0200-9
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- Article
Mass-Spectrometric Studies of Irradiated Uranium-Erbium Fuel.
- Published in:
- Atomic Energy, 2017, v. 121, n. 4, p. 283, doi. 10.1007/s10512-017-0198-z
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- Publication type:
- Article
Electropotential Monitoring: Nondestructive Method for Fast Assessment of Fuel-Element Cladding Condition in the BN-600 Reactor.
- Published in:
- Atomic Energy, 2017, v. 121, n. 4, p. 288, doi. 10.1007/s10512-017-0199-y
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- Publication type:
- Article
Physicochemical Interaction of EK-164 Steel with Uranium Dioxide During High-Temperature Irradiation.
- Published in:
- Atomic Energy, 2016, v. 120, n. 3, p. 199, doi. 10.1007/s10512-016-0117-8
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- Article
Interaction of fuel with ferrite-martensite steel fuel-element cladding under fast reactor conditions.
- Published in:
- Atomic Energy, 2013, v. 113, n. 5, p. 374, doi. 10.1007/s10512-013-9648-4
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- Article