Tensile and burst tests in support of the cadmium safety rod failure evaluation

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Description

The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of hypothetical LOCA event. Accordingly, an experimental safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. This report discusses confirmatory separate effects tests conducted to support the evaluation of failures observed in the safety rod thermal tests. As part of the failure evaluation, the potential for liquid metal embrittlement (LME) of the safety rod cladding by cadmium (Cd) -- aluminum (Al) solutions ... continued below

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Pages: (27 p)

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Thomas, J.K. February 1, 1992.

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Description

The reactor safety rods may be subjected to high temperatures due to gamma heating after the core coolant level has dropped during the ECS phase of hypothetical LOCA event. Accordingly, an experimental safety rod testing subtask was established as part of a task to address the response of reactor core components to this accident. This report discusses confirmatory separate effects tests conducted to support the evaluation of failures observed in the safety rod thermal tests. As part of the failure evaluation, the potential for liquid metal embrittlement (LME) of the safety rod cladding by cadmium (Cd) -- aluminum (Al) solutions was examined. Based on the test conditions, literature data, and U-Bend tests, its was concluded that the SS304 safety rod cladding would not be subject to LME by liquid Cd-Al solutions under conditions relevant to the safety rod thermal tests or gamma heating accident. To confirm this conclusion, tensile tests on SS304 specimens were performed in both air and liquid Cd-Al solutions with the range of strain rates, temperatures, and loading conditions spanning the range relevant to the safety rod thermal tests and gamma heating accident.

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Pages: (27 p)

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OSTI; NTIS; INIS; GPO Dep.

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  • Other: DE92015892
  • Report No.: WSRC-RP-92-314
  • Grant Number: AC09-89SR18035
  • DOI: 10.2172/5300586 | External Link
  • Office of Scientific & Technical Information Report Number: 5300586
  • Archival Resource Key: ark:/67531/metadc1067019

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

Office of Scientific and Technical Information (OSTI) is the Department of Energy (DOE) office that collects, preserves, and disseminates DOE-sponsored research and development (R&D) results that are the outcomes of R&D projects or other funded activities at DOE labs and facilities nationwide and grantees at universities and other institutions.

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  • February 1, 1992

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

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  • May 15, 2018, 4:16 p.m.

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Thomas, J.K. Tensile and burst tests in support of the cadmium safety rod failure evaluation, report, February 1, 1992; Aiken, South Carolina. (digital.library.unt.edu/ark:/67531/metadc1067019/: accessed June 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.