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- Alloy-Ht-9
- Specific Nuclear Reactors And Associated Plants 12
- Fuel Cans 11
- Materials Science 10
- Alloys 8
- Chromium Alloys 8
- Chromium Steels 8
- General Studies Of Nuclear Reactors 8
- Iron Alloys 8
- Iron Base Alloys 8
- Steels 8
- Chromium-Molybdenum Steels 7
- Burnup 6
- Fast Reactors 6
- Fuel Elements 6
- Lmfbr Type Reactors 6
- Testing 6
- Ebr-2 Reactor 5
- Epithermal Reactors 5
- Fftf Reactor 5
- Liquid Metal Cooled Reactors 5
- Physical Radiation Effects 5
- Reactors 5
- Stainless Steel-316 5
- Alloy-D-9 4
- Breeder Reactors 4
- Design 4
- Fbr Type Reactors 4
- Fuel Assemblies 4
- Fuel Pins 4
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1
Durability and degradation of HT9 based alloy waste forms with variable Ni and Cr content
Published 2016Online Access (via OSTI)
Government Document Electronic eBook -
2
Postirradiation examination of the HT9 clad fuel test X425 at 2.9% burnup
Published 1987Online Access (via OSTI)
Government Document Electronic eBook -
3
Demonstration of a high burnup heterogeneous core using ferritic/martensitic materials
Published 1986Online Access (via OSTI)
Government Document Electronic eBook -
4
Performance of 9 to 12% Cr-1 Mo steels during flattening test
Published 1981Online Access (via OSTI)
Government Document Electronic eBook -
5
Fuel/cladding compatibility of U-10Zr and U-5Fs fuels with advanced alloy cladding materials
Published 1985Online Access (via OSTI)
Government Document Electronic eBook -
6
Compatibility of low-burnup U-1OZr fuel with HT9 cladding at elevated temperatures
Published 1999Online Access (via OSTI)
Government Document Electronic eBook -
7
Fuel/cladding compatibility in low-burnup U-26Pu-10Zr/HT9 fuel at elevated temperatures
Published 1991Online Access (via OSTI)
Government Document Electronic eBook -
8
The reliability of untempered end plug welds on HT9-clad IFR fuel elements
Published 1987Online Access (via OSTI)
Government Document Electronic eBook -
9
Test Design Description Volume 2, Part 1, MFF-1 and MFF-1A metal fuel irradiations (HF168 and HF169) element as-built data.
Published 1987Online Access (via OSTI)
Government Document Electronic eBook -
10
Interdiffusion between U-Pu-Zr fuel and HT9 cladding
Published 1994Online Access (via OSTI)
Government Document Electronic eBook -
11
TOKOPS Tokamak Reactor Operations Study The influence of reactor operations on the design and performance of tokamaks with solid-breeder blankets Final report.
Published 1986Online Access
Government Document Electronic eBook -
12
Transmutations in fusion test facilities
Published 1986Online Access
Government Document Electronic eBook -
13
Fission-suppressed hybrid reactor the fusion breeder.
Published 1982Online Access (via OSTI)
Government Document Electronic eBook -
14
Design limits for HT9 cladding using stress-induced aging data
Published 1986Online Access (via OSTI)
Government Document Electronic eBook -
15
Chemical durability and degradation mechanisms of HT9 based alloy waste forms with variable Zr content
Published 2015Online Access
Government Document Electronic eBook -
16
Mechanical properties testing of several 800 MeV proton irradiated BCC metals and alloys. [Candidate window materials for SIN beam stop]
Published 1986Online Access
Government Document Electronic eBook -
17
Experience with advanced driver fuels in EBR-II
Published 1992Online Access (via OSTI)
Government Document Electronic eBook -
18
Performance of HT9 clad metallic fuel at high temperature
Published 1992Online Access (via OSTI)
Government Document Electronic eBook -
19
Performance of HT9 clad metallic fuel at high temperature
Published 1992Online Access (via OSTI)
Government Document Electronic eBook -
20
Experience with advanced driver fuels in EBR-II
Published 1992Online Access (via OSTI)
Government Document Electronic eBook