Actions for Axial location of cladding failure during a slow transient overpower TREAT test. [LMFBR] [electronic resource].
Axial location of cladding failure during a slow transient overpower TREAT test. [LMFBR] [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 axial location of cladding failure following a transient overpower accident is of importance in fast reactor safety studies in that it is a determining factor in the relocation of fuel, and therefore in the possibility of inherent neutronic shutdown of the reactor. In-pile experimental data on the axial location of cladding failure of fuel in bundles of pins is sparse since, in general, the experimental fuel pin bundles are largely destroyed during the in-pile test. The post-test examination work has been completed for TREAT test J1. It was found that damage to the fuel elements during the irradiation was low enough for an accurate observation of the location of cladding failure to be made for each of the seven pins.
- Report Numbers
- E 1.99:conf-830609-67
conf-830609-67 - Subject(s)
- Other Subject(s)
- Fuel Element Failure
- Fuel Pins
- Lmfbr Type Reactors
- Transient Overpower Accidents
- Test Facilities
- Fuel Cans
- Reactor Safety
- Thermal Stresses
- Treat Reactor
- Accidents
- Air Cooled Reactors
- Breeder Reactors
- Enriched Uranium Reactors
- Epithermal Reactors
- Experimental Reactors
- Fast Reactors
- Fbr Type Reactors
- Fuel Elements
- Gas Cooled Reactors
- Graphite Moderated Reactors
- Homogeneous Reactors
- Liquid Metal Cooled Reactors
- Reactor Accidents
- Reactor Components
- Reactors
- Research And Test Reactors
- Safety
- Solid Homogeneous Reactors
- Stresses
- Test Reactors
- Thermal Reactors
- Note
- Published through SciTech Connect.
01/01/1983.
"conf-830609-67"
"DE85004823"
ANS annual meeting, Detroit, MI, USA, 12 Jun 1983.
Holland, J.W.; Murphy, W.F.; Page, R.J. - Funding Information
- W-31-109-ENG-38
View MARC record | catkey: 14371975