Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

Dayal, R.; Lee, B.S.; Wilke, Richard; Swyler, K.J.; Soo, P.; Ahn, T.M.; McIntyre, N. S.; Veakis, E.

doi:10.2172/5441047

Cited by 3 publications

(4 citation statements)

References 3 publications

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“…In general, sec is accelerated by increasing temperature. Dayal et al (1982) reponed for stainless steels in . chloride environments a dependence of time to failure of the following fonn:…”

Section: Stress Corrosion Crackingmentioning

confidence: 99%

“…Use of clMy backfill as the outer portion of a waste package was first proposed to ;educe permeability (KBS, 1978a), control the composition of waters contacting containers (KBS, 1978b), and delay the onset of radionuclide release once containers have been breached (Clowak, 1979). Nowak (1979) and Dayal et aL (1982) derived formulas for the time delay resulting from diffusion through clay backfiH, but ChambrC and Pigford (1984) point out that these ! :ormulas overestimate the delay by calculating the time for the concentration to approach its maximum value in a semi-infinite medium, rather than the time course of the mass transport rate in a tintte medium.…”

Section: Backfillmentioning

confidence: 99%

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Methods of calculating the post-closure performance of high-level waste repositories

Ross¹

1989

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“…In general, sec is accelerated by increasing temperature. Dayal et al (1982) reponed for stainless steels in . chloride environments a dependence of time to failure of the following fonn:…”

Section: Stress Corrosion Crackingmentioning

confidence: 99%

Section: Backfillmentioning

confidence: 99%

Methods of calculating the post-closure performance of high-level waste repositories

Ross¹

1989

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“…A typical example of potential change before passivity breakdown is shown in Figure 1. The anode potential is increased during the early stage of immersion because of the growth of a barrier oxide (anatase Ti02)-^'^ After the raaximrm potential is reached, non-barrier oxide (rutile Ti02> forms and the following three types of potential change are dominant: (1) potential drop caused by oxygen concentration change,-(2) Ohmic potential drop,*^ (3) potential rise due to excess proton generation 11 (Junction Potential). These are less important before Che maximum potential is obtained.…”

Section: Crevice Corrosionmentioning

confidence: 99%

“…For stage II crack propagation which is controlled by hydride nucleation at the crack tip, the relationship is:^>ĝ -0.5 * I 3…”

Section: Hydrogen Embrittlementmentioning

confidence: 99%

Prediction of long term crevice corrosion and hydrogen embrittlement behavior of ASTM grade-12 titanium

Ahn¹,

Jain²

1984

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Crevice corrosion and hydrogen embrittlement are potential failure modes of Grade-12 titanium high-level nuclear waste containers emplaced in roclc salt repositories. A method is presented to estimate the environment domains for which immunity to these failure modes will exist for periods of hundreds of years. The estimation is based on the identification and quantification of mechanisms involved. Macroscopic concentration cell formation is responsible for crevice corrosion. The cell formation is accompanied by oxygen depletion, potential drop, anion accumulation and acidification inside the crevice. This process is quantified by simple mass balance equations which show that the immunity domain is a function of the time the container is exposed to the corrosion environment. Strain induced hydride formation is responsible for hydrogen assisted crack initiation. A simple model for slow cracsc growth is developed using data on growth rates measured at various temperatures. The parameters obtained in the model are used to estimate the threshold stress intensity and hydrogen solubility limit in the alloy at infinite container service time. This value gives a crack size below which container failure will not occur for a given applied stress and hydrogen concentration, and a hydrogen concentration limit at a given stress intensity. MASTER *This work was performed under the auspices of the United States Nuclear Regulatory Commission.

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Disposal of high-level nuclear waste above the water table in arid regions

Roseboom¹

1983

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Locating a repository in the unsaturated zone of arid regions eliminates or simplifies many of the technological problems involved in designing a repository for operation below the water table and predicting its performance. It also offers possible accessibility and ease of monitoring throughout the operational period and possible retrieval of waste long after. The risks inherent in such a repository appear to be no greater than in one located in the saturated zone; in fact, many aspects of such a repository's performance will be much easier to predice and the uncertainties will be reduced correspondingly. A major new concern would be whether future climatic changes could produce significant consequences due to pogsible rise of the water table or increased flux of water through the repository. If spent fuel were used as a waste form, a second new concern would be the rates of escape of gaseous iodine129 and carbon-14 to the atmosphere. * * * Such a system would be above, rather than below, the regional water table, and if properly engineered. should remain dry at least much of the time. It would have the advantages of greater ease of construction, greater distance from the [Columbia] river, easier retrieval of waste canisters if this should prove 'As knowledge of the Y u m Marntain site grew. some members of a Peer Review COmmiUee. made up of representatives from universities and indushy, raised questions as to the possible utilization of potential hmt rccks in theunsakatedme. In February 1982. several scientists of the U S Geological Survey (USGS). in a letter to the Department of Energy F'mgram Manager for the Nevada Nuclear Waste Storage Investigations Program.. sd the hydrogeologic eonditions that should be present in the unsaturated m e beneath Yucca Mountain and concluded that they should provide a very favorable envirmment for waste disposaL At about the same time, the USGS sent a letter to the Nuclear Regdatay Commission (NRC) suggesting how NRCpropased rule 10 CFR Part 60. which was specificaUy limited to repe3itories in the saturated m e , might be modiKed to include t h m in the UP sahrrated m e A subsequent draft of 10 CFR Part 60 covm both m e s .

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Nuclear waste management technical support in the development of nuclear waste form criteria for the NRC. Task 1. Waste package overview

Cited by 3 publications

References 3 publications

Methods of calculating the post-closure performance of high-level waste repositories

Methods of calculating the post-closure performance of high-level waste repositories

Prediction of long term crevice corrosion and hydrogen embrittlement behavior of ASTM grade-12 titanium

Disposal of high-level nuclear waste above the water table in arid regions

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