scholarly journals The Waste Package Project. Final report, July 1, 1995--February 27, 1996: Volume 1, The structural performance of the shell and fuel rods of a high level nuclear waste container

1996 ◽  
Author(s):  
Rajkumar Rajagopalan
Keyword(s):  
Nuclear Waste ◽  
Structural Performance ◽  
Final Report ◽  
Fuel Rods ◽  
Waste Package ◽  
Waste Container ◽  
High Level Nuclear Waste ◽  
High Level

scholarly journals Fabrication development for high-level nuclear waste containers for the tuff repository; Phase 1 final report

1990 ◽  
Author(s):  
H.A. Domian ◽  
R.L. Holbrook ◽  
D.F. LaCount
Keyword(s):  
Nuclear Waste ◽  
Phase 1 ◽  
Final Report ◽  
High Level Nuclear Waste ◽  
High Level

scholarly journals Effects of long-term exposure of tuffs to high-level nuclear waste repository conditions. Final report

10.2172/59938 ◽  
1986 ◽  
Author(s):  
J.D. Blacic ◽  
D.T. Vaniman ◽  
D.L. Bish ◽  
C.J. Duffy ◽  
R.C. Gooley
Keyword(s):  
Nuclear Waste ◽  
Nuclear Waste Repository ◽  
Final Report ◽  
High Level Nuclear Waste ◽  
Waste Repository ◽  
High Level

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 Selection of candidate container materials for the conceptual waste package design for a potential high level nuclear waste repository at Yucca Mountain

1993 ◽  
Author(s):  
R.A. Van Konynenburg ◽  
W.G. Halsey ◽  
R.D. McCright ◽  
W.L. Jr. Clarke ◽  
G.E. Gdowski
Keyword(s):  
Nuclear Waste ◽  
Yucca Mountain ◽  
Nuclear Waste Repository ◽  
Package Design ◽  
Waste Package ◽  
High Level Nuclear Waste ◽  
Waste Repository ◽  
High Level ◽  
Selection Of

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.

Effects of Surface Chromium Depletion on Localized Corrosion of Alloy 825 as a High-Level Nuclear Waste Container Material

CORROSION ◽  
1995 ◽  
Vol 51 (8) ◽  
pp. 618-624 ◽  
Author(s):  
D. S. Dunn ◽  
N. Sridhar ◽  
G. A. Cragnolino
Keyword(s):  
Nuclear Waste ◽  
Localized Corrosion ◽  
Chromium Depletion ◽  
Waste Container ◽  
High Level Nuclear Waste ◽  
High Level ◽  
Container Material
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