2-MW plasmajet facility thermal tests of concrete. [PWR and BWR] [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1977.
- Physical Description
- Pages: 128 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- A test was made in the 2-Megawatt Plasmajet Facility to obtain experimental data relative to the thermal response of concrete to incident heat flux. 14.6 cm diameter by 8.0 cm long concrete cylinders were positioned in a supersonic flow of heated nitrogen from an arc heater. The end of the concrete cylinders impacted by the flow were subjected to heat fluxes in the range of 0.13 to 0.35 kW/cm/sup 2/. Measurements included cold wall surface heat flux and pressure distributions, surface and indepth temperatures, ablation rates, and surface emission spectrographs. The test was part of the Sandia light water reactor safety research program and complements similar tests made in the Radiant Heat Facility at heat fluxes from 0.03 to 0.12 kW/cm/sup 2/. A description of the tests and a tabulation of test data are included.
- Report Numbers
- E 1.99:sand-77-0952
sand-77-0952 - Subject(s)
- Other Subject(s)
- Bwr Type Reactors
- Containment Shells
- Concretes
- Ablation
- Performance Testing
- Thermal Stresses
- Pwr Type Reactors
- Corium
- Meltdown
- Reactor Safety
- Temperature Gradients
- Test Facilities
- Accidents
- Building Materials
- Containment
- Materials
- Reactor Accidents
- Reactors
- Safety
- Stresses
- Testing
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
07/01/1977.
"sand-77-0952"
Goin, K.L.
Sandia Labs., Albuquerque, NM (USA) - Funding Information
- EY-76-C-04-0789
View MARC record | catkey: 14803876