Hostname: page-component-76fb5796d-22dnz Total loading time: 0 Render date: 2024-04-25T11:33:32.328Z Has data issue: false hasContentIssue false

A Large Block Heater Test for High Level Nuclear Waste Management,

Published online by Cambridge University Press:  15 February 2011

Wunan Lin
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
D. G. Wilder
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
J. A. Blink
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
S. C. Blair
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
T. A. Buscheck
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
R. S. Glass
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
W. E. Glassley
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
K. Lee
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
R. D. McCright
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
M. W. Owens
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
J. J. Roberts
Affiliation:
All At Lawrence Livermore National Laboratory, P.O.Box 808, Livermore, Ca 94550
Get access

Abstract

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 × 3 × 4.5 m was sawed and isolated at Fran Ridge, Nevada Test Site. Small blocks of the rock adjacent to the large block were 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 measured 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.

Type
Research Article
Copyright
Copyright © Materials Research Society 1995

Access options

Get access to the full version of this content by using one of the access options below. (Log in options will check for institutional or personal access. Content may require purchase if you do not have access.)

References

REFERENCES

[1]. Montazer, P. M., and Wilson, W. E. (1984), “Conceptual hydrologic model of flow in the unsaturated zone, Yucca Mountain, Nevada,” USGS–84–4345 Water Resources Investigative Report, U.S. Geol. Survey, Denver. CO. (NNA.890327.0051)Google Scholar
[2]. Ramirez, A. L. (1991). Prototype Engineered Barrier System Field Test (PEBSFT) Final Report, Lawrence Livermore National Laboratory, UCRL–ID–106159. (NNA. 910711.0047)Google Scholar
[3]. Buscheck, T. A., Wilder, D. G., and Nitao, J. J. (1993), “Large-Scale In Situ Heater Tests for Hydrothermal Characterization at Yucca Mountain”, in High Level Radioactive Waste Management, Proceedings of the Fourth Annual International Conference, Las Vegas, Nevada, April 26 – 30, 1993, American Nuclear Society, La Grange Park, IL, also Lawrence Livermore National Laboratory, UCRL–JC–112445. (NNA.930217.0046)Google Scholar
[4]. Daily, W. D., Lin, W., and Buscheck, T. (1987), “Hydrological Properties of Topopah Spring Tuff: Laboratory Measurements,” J. Geophys. Res., Vol. 92, No. B8. pp. 78547864. (NNA.900123.0064)Google Scholar
[5]. Daily, W. D., and Ramirez, A. L. (1989), “Evaluation of Electromagnetic Tomography to Map In Situ Water in Heated Welded Tuff,” Water Resources Research, Vol. 25, No. 6, pp. 10831096. (NNA.910326.0097)Google Scholar
[6]. Lin, W., Ramirez, A. L., and Watwood, D. (1991,) “Temperature Measurements,” Chapter 7 of Prototype Engineered Barrier System Field Test (PEBSFT) Final Report, Ramirez, A. L., Sci. Ed., Lawrence Livermore National Laboratory Livermore, CA, UCRL–ID–106159, pp. 8293. (NNA.910711.0047)Google Scholar
[7]. Lin, W., and Daily, W. (1989), “Laboratory Study of Fracture Healing in Topopah Spring Tuff -Implications for Near Field Hydrology,” Proceedings of the Topical Meeting on Nuclear Waste Isolation in the Unsaturated Zone, Focus ’89, American Nuclear Society, La Grange Park, IL. (NNA.900711.0241)Google Scholar
[8]. Lin, W., and Daily, W. (1990), “Hydrological Properties of Topopah Spring Tuff under a Thermal Gradient -- Laboratory Results,” Int. J. Rock Mech. Min. Sci. & Geomech. Abstr. Vol. 27, No. 5, pp. 373385. (Readily Available)Google Scholar
[9]. Lin, W. (1991), “Variation of Permeability with Temperature in Fractured Topopah Spring Tuff Samples,” in High Level Radioactive Waste Management, Proceedings of the Second Annual International Conference, Las Vegas, Nevada, April 28 - May 3, 1991, American Nuclear Society, La Grange Park, IL, pp. 988993. (NNA.910523.0105)Google Scholar
[10]. Lin, W. (1993), Technical Basis and Programmatic Requirements for Large Block Testing of Coupled Thermal-Mechanical-Hydrological-Chemical Processes, Lawrence Livermore National Laboratory, Livermore, CA, UCRL–ID–112834. (NNA.930903.0075)Google Scholar
[11]. Kim, K. and McCage, W. M. (1984), “Geomechanics Characterization of the Candidate Nuclear Waste Repository Site in Basalt”, Proceedings in the 25th U.S. Symposium on Rock Mechanics, pp. 874882. (NNA.891212.0018)Google Scholar
[12]. Zimmerman, R. M., and Blanford, M. K. (1986), “Expected Thermal and Hydrothermal Environments for Waste Emplacement Holes Based on G-Tunnel Heater Experiments,” in 27th U.S. Symposium on Rock Mechanics, Hartman, H., Ed., (Society of Mining Engineers, Inc., Littleton, CO), pp. 874882. (NNA.891212.0018)Google Scholar
[13]. Wilder, D. G. (1993), “Alternative Strategies -- A Means for Saving Money and Time on the Yucca Mountain Project,” in High Level Radioactive Waste Management, Proceedings of the Fourth Annual International Conference, Las Vegas, Nevada, April 26–30, 1993, American Nuclear Society, La Grange Park, IL, pp. 12631270, also Lawrence Livermore National Laboratory, UCRL–JC–111652. (NNA.930224.0019)Google Scholar
[14]. Foltz, S. D., Tidwell, V. C., Glass, R. J., Kelsey, C. A., and Eaton, R. R. (1992), “An Experimental Investigation of Matrix Interaction on Fracture Flow,” EOS Transactions, 1992, Fall Meeting, American Geophysical Union, San Francisco, CA, December 7–1, p.223. (Abstract-readily available)Google Scholar
[15]. Tidwell, V. C., and Glass, R. J. (1992), “X-ray and Visible Light Transmission as Two-dimensional, Full-field Moisture-sensing Techniques: A Preliminary Comparison,” High Level Radioactive Waste Management, Proceedings of the Third International Conference, April 12–16, 1992, American Nuclear Society, La Grange Park, IL, and American Society of Civil Engineers, New York, NY, pp. 10991110. (NNA.930205.0015)Google Scholar
[16]. Danko, G., and Mousset-Jones, P. F., (1991), “A Probe Method for Measuring In Situ Thermophysical Properties,” in Proceedings, 2nd International High Level Radioactive Waste Management Conference, Las Vegas, NV, April 28-May 3, 1991, American Nuclear Society, La Grange Park, IL, pp. 555563. (Readily Available)Google Scholar