A large block heater test for high level nuclear waste management

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The radioactive decay heat from nuclear waste packages may, depending on the thermal load, create coupled thermal-mechanical-hydrological-chemical (TMHC) processes in the near-field environment of a repository. A group of tests on a large block (LBT) are planned to provide a timely opportunity to test and calibrate some of the TMHC model concepts. The LBT is advantageous for testing and verifying model concepts because the boundary conditions are controlled, and the block can be characterized before and after the experiment. A block of Topopah Spring tuff of about 3 {times} 3 {times} 4.5 m will be sawed and isolated at Fran ... continued below

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13 p.

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Lin, W.; Wilder, D.G. & Blink, J.A. July 1, 1994.

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Description

The radioactive decay heat from nuclear waste packages may, depending on the thermal load, create coupled thermal-mechanical-hydrological-chemical (TMHC) processes in the near-field environment of a repository. A group of tests on a large block (LBT) are planned to provide a timely opportunity to test and calibrate some of the TMHC model concepts. The LBT is advantageous for testing and verifying model concepts because the boundary conditions are controlled, and the block can be characterized before and after the experiment. A block of Topopah Spring tuff of about 3 {times} 3 {times} 4.5 m will be sawed and isolated at Fran Ridge, Nevada Test Site. Small blocks of the rock adjacent to the large block will be collected for laboratory testing of some individual thermal-mechanical hydrological and chemical processes. A constant load of about 4 MPa will be applied to the top and sides of the large block. The sides will be sealed with moisture and thermal barriers. The large block will be heated by heaters within and guard heaters on the sides so that a dry-out zone and a condensate zone will exist simultaneously. Temperature, moisture content, pore pressure, chemical composition, stress, and displacement will be throughout the block during the heating and cool-down phases. The results from the experiments on small blocks and the tests on the large block will provide a better understanding of some concepts of the coupled TMHC processes. The progress of the project is presented in this paper.

Physical Description

13 p.

Notes

INIS; OSTI as DE95002403

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  • 18. international symposium on the scientific basis for nuclear waste management, Kyoto (Japan), 23-27 Oct 1994

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  • Other: DE95002403
  • Report No.: UCRL-JC--116431
  • Report No.: CONF-941075--3
  • Grant Number: W-7405-ENG-48
  • Office of Scientific & Technical Information Report Number: 145607
  • Archival Resource Key: ark:/67531/metadc620318

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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.

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  • July 1, 1994

Added to The UNT Digital Library

  • June 16, 2015, 7:43 a.m.

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  • Feb. 17, 2016, 12:57 p.m.

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Lin, W.; Wilder, D.G. & Blink, J.A. A large block heater test for high level nuclear waste management, article, July 1, 1994; California. (digital.library.unt.edu/ark:/67531/metadc620318/: accessed October 20, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.