Salt Disposal of Heat-Generating Nuclear Waste

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Grauer, R., B. Knecht, P. Kreis, and J.P. Simpson. 1991. “Hydrogen Evolution from Corrosion of Iron and Steel in Intermediate Level Waste Repositories.” Scientific Basis for Nuclear Waste Management XIV, Materials Research Society Symposium Proceedings, Boston, MA, November 26–29, 1990. Vol. 44. Eds. T.A. Abrajano, Jr., and L.H. Johnson. Pittsburgh: Materials Research Society. 295– 302. Guzowski, R.V., and G. Newman. 1993. Preliminary Identification of Potentially Disruptive Scenarios at the Greater Confinement Disposal Facility, Area 5 of the Nevada Test Site. SAND93-7100. Albuquerque: Sandia National Laboratories. Haberman, J.H., and D.J. Frydrych. 1988. “Corrosion Studies of A216 Grade WCA Steel in Hydrothermal Magnesium-Containing Brines.” Scientific Basis for Nuclear Waste Management XI, Materials Research Society Symposium Proceedings, Boston, MA, November 30–December 3, 1987. Vol. 112. M.J. Apted and R.E. Westerman (eds.). Pittsburgh: Materials Research Society. 761–72. Hampel, A., R.M. Günther, K. Salzer, W. Minkley, A. Pudewills, B. Leuger, D. Zapf, K. Staudtmeister, R. Rokahr, K. Herchen, R. Wolters, K.-H. Lux, O. Schulze, U. Heemann, and U. Hunsche. 2010. Benchmarking of Geomechanical Constitutive Models for Rock Salt. Salt Lake City: American Rock Mechanics Association. Hansen, F.D. 2003. The Disturbed Rock Zone at the Waste Isolation Pilot Plant. SAND2003-3407. Albuquerque: Sandia National Laboratories. Hansen, F.D. 2010. Salt Rock Mechanics—Prediction vs. Performance—WIPP Provides the Answers. SAND2009-0866J. Albuquerque: Sandia National Laboratories. Hansen, F.D., and K.D. Mellegard. 1977. Creep Behavior of Bedded Salt from Southeastern New Mexico at Elevated Temperature. SAND79-7030. Albuquerque: Sandia National Laboratories. Hansen, F.D., and K.D. Mellegard. 1980. Further Creep Behavior of Bedded Salt from Southeastern New Mexico at Elevated Temperature. SAND80-7114. Albuquerque: Sandia National Laboratories. Hansen, F.D., and M.K. Knowles. 2000. “Design and Analysis of a Shaft Seal System for the Waste Isolations Pilot Plant.” Reliability Engineering and System Safety 69(1–3): 87–98. SAND99-0904J. Hansen, F.D., and J.S. Stein. 2006. WIPP Room Evolution and Performance Assessment Implications. Golden, CO: American Rock Mechanics Association. Hansen, F.D., E.L. Hardin, and A. Orrell. 2011. Geologic Disposal Options in the USA. SAND2010-7975C. Waste Management Conference, Phoenix, AZ. 78
Hansen, F.D., E.L. Hardin, R.P. Rechard, G.A. Freeze, D.C. Sassani, P.V. Brady, C.M. Stone, M.J. Martinez, J.F. Holland, T. Dewers, K.N. Gaither, S.R. Sobolik, and R.T. Cygan. 2010. Shale Disposal of U.S. High-Level Radioactive Waste. SAND2010-2843. Albuquerque: Sandia National Laboratories. Hardy, R.D., and D.J. Holcomb. 2000. “Assessing the Disturbed Rock Zone (DRZ) Around a 655-Meter Vertical Shaft in Salt Using Ultrasonic Waves, An Update.” Proceedings: Fourth North American Rock Mechanics Symposium (NARMS). Eds. J. Girard, M. Liebman, C. Breeds, and T. Doe. Brookfield, VT: A.A. Balkema. 1353–60. Harvie, C.E. 1981. Theoretical Investigations in Geochemistry and Atom Surface Scattering. PhD Dissertation. San Diego: University of California-San Diego. Harvie, C.E., N. Møller, and J.H. Weare. 1984. “The Prediction of Mineral Solubilities in Natural Waters: The Na-K-Mg-Ca-H-Cl-SO 4 -OH-HCO 3 -CO 3 -CO 2 - H 2 O System to High Ionic Strengths at 25°C.” Geochimica et Cosmochimica Acta 48(4): 723–51. Holcomb, D.J. 1999. “Assessing the Disturbed Rock Zone (DRZ) Around a 655- Meter Vertical Shaft in Salt Using Ultrasonic Waves.” Proceedings of the 37th U.S. Symposium on Rock Mechanics. Brookfield, VT: A.A. Balkema. 965–72. SAND2000-0668C. Holcomb, D.J., and R.D. Hardy. 2001. “Assessing the Disturbed Rock Zone (DRZ) at the Waste Isolation Pilot Plant in Salt Using Ultrasonic Waves Characteristics of the DRZ”. Proceedings of the 38th U.S. Symposium on Rock Mechanics. Brookfield, VT: A.A. Balkema. Paper 01-0489. Hunsche, U., and O. Schulze. 2000. “Measurement and Calculation of the Evolution of Dilatancy and Permeability in Rock Salt.” Proc. 3: Workshop über Kluft-Aquifere “Gekoppelte Prozesse in Geosystemen.” Hannover, Germany: University of Hannover. 107–13. International Atomic Energy Agency (IAEA). 2006. Safety Requirements for Geological Disposal of Radioactive Waste. WS-R-4. Vienna: IAEA. International Commission on Radiological Protection (ICRP). 1997. Radiological Protection Policy for the Disposal of Radioactive Waste. Annals of the ICRP 77. Tarrytown, NY: Permagon Press. Johnson, K.S., and S. Gonzales. 1978. Salt Deposits in the United States and Regional Geologic Characteristics Important for Storage of Radioactive Waste. Y/OWI/SUB-7414/1. Athens, GA: Earth Resources Associates. Karlsruher Institut für Technologie. 2010. Proceedings of the US-German Workshop on Salt Repository Research, Design, and Operation. Canton, MS: Mississippi State University. 79
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SANDIA REPORT SAND2011-0161 Unlimit
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SAND2011-0161 Unlimited Release Pri
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CONTENTS 1 Introduction ...........
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NOMENCLATURE CFR DOE DRZ EPA FEP HL
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1 INTRODUCTION While the need for i
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that deep geologic disposal in salt
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To the extent that regulatory guida
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Table 1. Salt and potash mines in t
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steel canisters and horizontal plac
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Considerable qualitative support fo
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Table 2. Qualitative comparison of
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Source: Sandia National Laboratorie
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2.2 Salt Repository Design A mine l
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placed over the waste canisters for
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other possible modes of interferenc
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provides frame of reference for sha
Page 34 and 35:
Healing conditions are created once
Page 36 and 37: permeability tests on Salado salt s
Page 38 and 39: terms of principal stresses. Stress
Page 40 and 41: Cross-hole and same-hole velocity m
Page 42 and 43: Figure 4. DRZ development and heali
Page 44 and 45: can be limited, changed, or otherwi
Page 46 and 47: natural salt extracted from the rep
Page 48 and 49: The thermal properties of the crush
Page 50 and 51: mechanical behavior and hydraulic p
Page 52 and 53: educing conditions is the reaction
Page 54 and 55: materials would also have an impact
Page 56 and 57: coefficient models exist (e.g., the
Page 58 and 59: and international researchers toget
Page 60 and 61: a very high level for the purpose o
Page 62 and 63: epresented in the FEP list, undersc
Page 64 and 65: • Response of the modified system
Page 66 and 67: analysis and performance assessment
Page 68 and 69: 4.4 Availability and Movement of Br
Page 70 and 71: Recent developments in Germany and
Page 72 and 73: 6. Damage Induced Permeability. Mec
Page 75 and 76: 5 SUMMARY AND RECOMMENDATIONS Deep
Page 77 and 78: 7. A HLW repository in salt is expe
Page 79 and 80: This analysis only addresses genera
Page 81: enchmarking program would continue
Page 84 and 85: Brodsky, N.S. 1990. Crack Closure a
Page 88 and 89: Knipping, B. 1989. Basalt Intrusion
Page 90 and 91: Plummer, L.N., D.L. Parkhurst, G.W.
Page 92 and 93: Wawersik, W.R., and D.W. Hannum. 19
Page 94 and 95: In the FEPs numbering scheme for WI
Page 96 and 97: WIPP FEP ID — FEP Name — Descri
Page 108 and 109: 1 Jack Moody Director, State Minera
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Salt Disposal of Heat-Generating Nuclear Waste

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