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Revisiting the 1980's WIPP room D and B in-situ experiments: Performing thermo-mechanical simulations of rock salt using a state-of-the-art code suite

47th US Rock Mechanics / Geomechanics Symposium 2013

Arguello, Jose G.; Rath, Jonathan S.

Several "Thermal/Structural Interactions" full-scale in-situ experiments were fielded at the Waste Isolation Pilot Plant in the mid 1980's. Data from two of these experiments, the Mining Development Test (Room D) and the Overtest for Simulated Defense High-Level Waste (Room B), havebeen used previously to help validate the legacy constitutive models and computer codes used to assess the performance of the disposal facility prior to its licensing and operation. Since then, approximately 30 years of software and hardware advances have yielded efficient software frameworks and enabling tools/infrastructure to produce a new generation of high-fidelity simulation tools. One such current state-of-the-art modeling capability is the computer code suite, SIERRA Mechanics. The capability to model waste repositories is a relatively recent addition to SIERRA Mechanics. Consequently, datafrom the same two WIPP rooms D &B are used in an effort, described herein, aimed at validating the code suite to this class of problems. WIPP Rooms D &B are also being proposed for an international benchmarking exercise between US and German researchers. A review of the salient features for these two rooms that need to be captured in such an exercise will also be described and elaborated. Copyright 2013 ARMA, American Rock Mechanics Association.

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Radioactive and nonradioactive waste intended for disposal at the Waste Isolation Pilot Plant

Reliability Engineering and System Safety (Special Journal Issue)

Sanchez, Lawrence C.; Rath, Jonathan S.

Transuranic (TRU) waste generated by the handling of plutonium in research on or production of US nuclear weapons will be disposed of in the Waste Isolation Pilot Plant (WIPP). This paper describes the physical and radiological properties of the TRU waste that will be deposited in the WIPP. This geologic repository will accommodate up to 175,564 m{sup 3} of TRU waste, corresponding to 168,485 m{sup 3} of contact-handled (CH-) TRU waste and 7,079 m{sup 3} of remote-handled (RH-) TRU waste. Approximately 35% of the TRU waste is currently packaged and stored (i.e., legacy) waste, with the remainder of the waste to be packaged or generated and packaged in activities before the year 2033, the closure time for the repository. These wastes were produced at 27 US Department of Energy (DOE) sites in the course of generating defense nuclear materials. The radionuclide and nonradionuclide inventories for the TRU wastes described in this paper were used in the 1996 WIPP Compliance Certification Application (CCA) performance assessment calculations by Sandia National Laboratories/New Mexico (SNL/NM).

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14 Results
14 Results