Eutectic penetration times in irradiated EBR-II driver fuel elements [electronic resource].
- Published:
- Argonne, Ill. : Argonne National Laboratory, 1983.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: 5 : digital, PDF file
- Additional Creators:
- Argonne National Laboratory and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- The experimental test procedure employed the use of a high-temperature furnace which heated pre-irradiated elements to temperature and maintained the environment until element-cladding breach occurred. Pre-irradiated elements of the Mark-II design were first encapsulated in a close-fitting sealed tube that was instrumented with a pressure transducer at the top of the tube and a thermocouple at the element's top-of-fuel axial location. The volume of the capsule was evacuated in order to better identify the pressure pulse which would occur on breach and to minimize contaminants. Next, a three-zone fast-recovery furnace was heated and an axial temperature profile, similar to that experienced in the EBR-II core, was established. The encapsulated element was then quickly inserted into the furnace and remained there until clad breach occurred. The element was then removed from the furnace immediately. Visual and metallurgical examination of the rupture site was done later. A total of seven elements were tested in the above manner.
- Report Numbers:
- E 1.99:conf-831047-75
conf-831047-75 - Subject(s):
- Other Subject(s):
- Ebr-2 Reactor
- Fuel Element Failure
- Fuel Pins
- Burnup
- Eutectics
- Fuel Cans
- Thermal Stresses
- Accidents
- Breeder Reactors
- Epithermal Reactors
- Experimental Reactors
- Fast Reactors
- Fbr Type Reactors
- Fuel Elements
- Liquid Metal Cooled Reactors
- Lmfbr Type Reactors
- Power Reactors
- Reactor Accidents
- Reactor Components
- Reactors
- Research And Test Reactors
- Sodium Cooled Reactors
- Stresses
- Note:
- Published through SciTech Connect.
01/01/1983.
"conf-831047-75"
"DE83015377"
American Nuclear Society winter meeting, San Francisco, CA, USA, 30 Oct 1983.
Seidel, B.R.; Betten, P.R.; Bottcher, J.H. - Funding Information:
- W-31-109-ENG-38
View MARC record | catkey: 14802253