scholarly journals Seismic structural analysis of a conceptual waste package design for disposal of high level nuclear waste in a geologic repository

1995 ◽  
Author(s):  
Z. Ceylan ◽  
S.M. Bennett ◽  
T.W. Doering
Keyword(s):  
Structural Analysis ◽  
Nuclear Waste ◽  
Geologic Repository ◽  
Package Design ◽  
Waste Package ◽  
High Level Nuclear Waste ◽  
High Level

Waste Package Reliability / Nalysis

1983 ◽  
Vol 26 ◽  
Author(s):  
C. Pescatore ◽  
C. Sastre
Keyword(s):  
Ordinary Sense ◽  
Regulatory Requirements ◽  
Package Design ◽  
Waste Package ◽  
Qualitative And Quantitative ◽  
Future Performance ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Package Reliability ◽  
General Method

ABSTRACTProof of future performance of a complex system such as a high-level nuclear waste package over a period of hundreds to thousands of years cannot be had in the ordinary sense of the word. The general method of probabilistic reliability analysis could provide an acceptable framework to identify, organize, and convey the information necessary to satisfy the criterion of reasonable assurance of waste package performance according to the regulatory requirements set forth in 10 CFR 60. General principles which may be used to evaluate the qualitative and quantitative reliability of a waste package design are indicated and illustrated with a sample calculation of a repository concept in basalt.

Structural analysis of some sodium and alumina rich high-level nuclear waste glasses

2012 ◽  
Vol 358 (3) ◽  
pp. 674-679 ◽  
Author(s):  
Ashutosh Goel ◽  
John S. McCloy ◽  
Kevin M. Fox ◽  
Clifford J. Leslie ◽  
Brian J. Riley ◽  
...  
Keyword(s):  
Structural Analysis ◽  
Nuclear Waste ◽  
High Level Nuclear Waste ◽  
High Level

Comparison of CFD Calculations With Experimental Results for the YMP Scaled Natural Convection Tests

2004 ◽  
Author(s):  
Sandra Dalvit Dunn ◽  
Stephen W. Webb ◽  
John Del Mar ◽  
Michael T. Itamura ◽  
Nicholas D. Francis
Keyword(s):  
Nuclear Waste ◽  
Pilot Scale ◽  
Department Of Energy ◽  
Geologic Repository ◽  
Specific Data ◽  
Concrete Pipe ◽  
High Level Nuclear Waste ◽  
High Level ◽  
And Control ◽  
Calculated Model

The Yucca Mountain Project (YMP) is currently designing a geologic repository for high level nuclear waste. The design encompasses two distinct phases, the pre-closure period where temperatures within the repository will be controlled by active ventilation, and the post-closure period where the repository will be sealed. A prerequisite for designing the repository is the ability to both understand and control the heat generated from the decay of the nuclear waste. This decay heat affects the performance of both the waste packages and the emplacement drift. The ability to accurately model the complex heat transfer within the repository is critical to the understanding of the repository performance. Currently, computational fluid dynamics codes are being used to model the post-closure performance of the repository. Prior to using the codes on the project they were required to be thoroughly validated. Eight pilot-scale tests were performed at the Department of Energy North Las Vegas Atlas Facility to evaluate the processes that govern thermal transport in an environment that scales to the proposed repository environment during the post closure period. The tests were conducted at two geometric scales (25 and 44% of full scale), with and without drip shields, and under both uniform and distributed heat loads. The tests provided YMP specific data for model validation. A separate CFD model was developed for each of the four test configurations. The models included the major components of the experiment, including the waste packages (heated steel canisters), invert floor, and emplacement drift (insulated concrete pipe). The calculated model temperatures of the surfaces and fluids, and velocities, are compared with experimental data.

Evaluation of the Susceptibility of Astm A216 Grade Wca Mild Steel to Stress Corrosion Cracking in Simulated Salt Repositopy Environments

1986 ◽  
Vol 84 ◽  
Author(s):  
S. G. Pitman
Keyword(s):  
Mild Steel ◽  
Stress Corrosion ◽  
Nuclear Waste ◽  
Dynamic Tests ◽  
Static Tests ◽  
Waste Package ◽  
Test Conditions ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Container Material

AbstractIn current conceptual designs, a mild steel (ASTM A?16 Grade WCA) is the relerence container material for use in high level nuclear waste packages intended for emplacement in a salt repository. The resistance of the steel to stress corrosion crackinq (SCC) is being investigated as part of the effort underway to verify the suitability of the material for waste package applications. Static tests (U-bend and bolt-loaded fracture toughness specimens) and dynamic tests (slow strain rate and corrosion fatigue) were conducted on both as-cast and weldment specimens of the material, in both low-Mg and high-Mg halite-saturated brines, in the temperature range of 90 to 200°C. The investigations indicate that the steel is not susceptible to SCC under the test conditions employed.

scholarly journals Functions of the Materials Review Board

1984 ◽  
Vol 44 ◽  
Author(s):  
M. J. Steindler ◽  
W. B. Seefeldt
Keyword(s):  
Nuclear Waste ◽  
Environmental Protection Agency ◽  
Nuclear Regulatory Commission ◽  
Department Of Energy ◽  
Waste Package ◽  
Performance Predictions ◽  
High Level Nuclear Waste ◽  
Regulatory Commission ◽  
High Level ◽  
Nuclear Waste Policy

Some nuclear waste is destined for disposal in deep geological formations. The disposal system for wastes from commercial nuclear activities, and perhaps also for high-level wastes from defense-related activities, is to be designed and operated by the Department of Energy (DOE) and licensed by the Nuclear Regulatory Commission (NRC). The Nuclear Waste Policy Act [1] outlines some of the procedures and schedules that are to be followed by DOE in carrying out its assignment in the disposal of high-level nuclear waste (HLW). The regulations of the NRC that deal with HLW [2] are only partly in place, and amendments (e.g., related to the unsaturated zone) are yet to be approved and issued. The Environmental Protection Agency (EPA) has issued only draft versions of the regulations pertaining to HLW disposal [3], but key features of these drafts are at present in adequate agreement with NRC documents. On the basis of the trends that have become evident in the last few years, the DOE will be required to substantiate performance predictions for all pertinent aspects of a repository, especially the performance of the engineered waste package. The basis for demonstrating that the waste package performance in the repository will be in concert with the requirements is data on the waste package materials. These key materials data must clearly be highly reliable, and DOE will be required to assure this reliability. This paper addresses the organization and functions that have been assembled to aid in establishing the quality of materials data that are important in the licensing of a waste repository.

Development of a Backfill for Containment of High-Level Nuclear Waste

1981 ◽  
Vol 11 ◽  
Author(s):  
Floyd N. Hodges ◽  
Joseph H. Westsik ◽  
Lane A. Bray
Keyword(s):  
Thermal Conductivity ◽  
Thermal Diffusivity ◽  
Nuclear Waste ◽  
Release Rate ◽  
Sodium Bentonite ◽  
Waste Package ◽  
Diffusivity Measurements ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Host Rocks

ABSTRACTSodium and calcium bentonites, pressed to densities between 1.9 and 2.2 g/cm3, have hydraulic conductivities in the range of 10−11 to 10−13 cm/s. Batch sorption distribution ratios (Rd) indicate that Sr, Cs, and Am are strongly sorbed on bentonites and zeolites, that Np and U are moderately sorbed on bentonites and zeolites, and that Am, Np, U, I, and Tc are strongly sorbed on charcoal. Sorption results with basalt and tuff ground waters are similar; however, iodine in tuff ground water sorbs more strongly on bentonites Thermal diffusivity measurements for dry, compacted (p ∼ 2.1 g/cm3) sodium bentonite indicate that the thermal conductivity of a high density bentonite backfill should be roughly similar to that of silicate host rocks (basalt, granite, tuff). These results indicate that a bentonite backfill can significantly delay the first release of many radionuclides into the host rock and that by forming a diffusion barrier a bentonite backfill can significantly decrease the longterm release rate of radionuclides from the waste package.

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