Simulated Boiling Water Reactor and Superheat Reactor Corrosion Facility
- 1 September 1963
- journal article
- research article
- Published by Taylor & Francis in Nuclear Science and Engineering
- Vol. 17 (1) , 18-29
- https://doi.org/10.13182/nse63-a17206
Abstract
A versatile boiling water and superheated steam facility has been developed for out-of-pile corrosion testing of materials that are being used and considered for application in boiling water reactor (BWR) and superheat reactor (SHR) systems. The following capabilities have been achieved: 1. Simulation of the various environments (other than irradiation) that would contact materials in a Dresden type BWR and an SHR utilizing steam generated therefrom. Test space is available at 1000 psi in saturated steam, steam-water mixture and saturated water at 546°F and in superheated steam at 1050°F.2. Dynamic fuel-cladding material tests operated with a heat flux of 250,000 Btu/hr-ft2 for testing tubular type cladding under representative BWR heat transfer conditions.3. Dynamic fuel-cladding-material tests operated with a heat flux of 170,000 Btu/hr-ft2 for testing tubular cladding under representative SHR heat-transfer conditions.4. Control of oxygen and hydrogen content in the steam and water to simulate the gas c...Keywords
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