Behavior of Carbon-14 in Waste Packages for Spent Fuel in a Repository in Tuff

Konynenburg, R.A. Van; Smith, C. F.; Culham, H. W.; Otto, Christopher

doi:10.1557/proc-44-405

Cited by 5 publications

(4 citation statements)

References 10 publications

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“…There is evidence (Van Konynenburg et al 1985) of rapid release of 14 c, probably as co 2 gas, from the outside surface of intact cladding at 275°C in air. Approximately 0.3% of the calculated 1 4 c inventory for the total spent fuel assembly was released.…”

Section: Claddingmentioning

confidence: 99%

“…The likely release mechanisms of radionuclides, particularly 14c, from spent fuel cladding are reviewed in Appendix D. Two separate release rate cases are used in the WPR model, depending on whether water or steam is present at the time of container failure. If steam conditions prevail at the time of container failure, a significant amount of 14 c from the crud layer on the oJter surface of the cladding can be released as co 2 gas (Van Konynenburg et al 1985). There is uncertainty in assessing the total amount of 14c existing 1n the cladding (thus, the proportion released) and the distribution of 14 c throughout the cladding (Appendix D).…”

Section: Wpr Modeling ~~Ent Fuelmentioning

confidence: 99%

“…In particular, the cladding contains an appreciable fraction of the total 1 4 c inventory of spent fuel (Van Konynenburg et al 1985). This 14c is formed as an activation product of (n,p) reaction of 14N impurities and from (n, a) reaction of 17o.…”

Section: Claddingmentioning

confidence: 99%

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The Analytical Repository Source-Term (AREST) model: Description and documentation

Liebetrau¹,

Apted²,

Engel³

et al. 1987

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The Office of Civilian Radioactive Waste Management (OCRWM) of the U.S. Department of Energy {DO£) has a mission to provide for the permanent disposal of radioactive wastes in deep geologic repositories. The OCRWM is currently developing a performance assessment strategy for demonstrating compliance with the safety and performance criteria developed by the U.S. Nuclear Regulatory Commission (NRC) and the U.S. Environmental Protection Agency (EPA). Because of the long time (more than 10,000 years) involved, the OCRWM performance assessment strategy necessarily relies upon computerized models of the geologic repository system and its components.

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Section: Claddingmentioning

confidence: 99%

Section: Wpr Modeling ~~Ent Fuelmentioning

confidence: 99%

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The Analytical Repository Source-Term (AREST) model: Description and documentation

Liebetrau¹,

Apted²,

Engel³

et al. 1987

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“…C-14 releases have been separately analyzed and modeled during SF oxidation in dry environments (Ahn, 1994). For details on this C-14 behavior, the reader is referred to k ' m (1994) and related papers such as those by Codell (1993) or Van Konynenburg (1994). Summarizing the author's work, higher oxide formation may release C-14 from bare SF, significantly for 10,000 years in terms of its inventory, under anticipated dry conditions.…”

Section: Fracture Pathmentioning

confidence: 99%

Dry oxidation and fracture of LWR spent fuels

Ahn¹

1996

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Modeling of thermally driven hydrological processes in partially saturated fractured rock

Tsang¹,

Birkhölzer²,

Mukhopadhyay³

2009

Reviews of Geophysics

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[1] This paper is a review of the research that led to an indepth understanding of flow and transport processes under strong heat stimulation in fractured, porous rock. It first describes the anticipated multiple processes that come into play in a partially saturated, fractured porous volcanic tuff geological formation when it is subject to a heat source such as that originating from the decay of radionuclides. The rationale is then given for numerical modeling being a key element in the study of multiple processes that are coupled. The paper outlines how the conceptualization and the numerical modeling of the problem evolved, progressing from the simplified to the more realistic. Examples of numerical models are presented so as to illustrate the advancement and maturation of the research over the last 2 decades. The most recent model applied to in situ field thermal tests is characterized by (1) incorporation of a full set of thermal-hydrological processes into a numerical simulator, (2) realistic representation of the field test geometry in three dimensions, and (3) use of site-specific characterization data for model inputs. Model predictions were carried out prior to initiation of data collection, and the model results were compared to diverse sets of measurements. The approach of close integration between modeling and field measurements has yielded a better understanding of how coupled thermal hydrological processes produce redistribution of moisture within the rock, which affects local permeability values and subsequently the flow of liquid and gases. The fluid flow, in turn, will change the temperature field. We end with a note on future research opportunities, specifically those incorporating chemical, mechanical, and microbiological factors into the study of thermal and hydrological processes.

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Behavior of Carbon-14 in Waste Packages for Spent Fuel in a Repository in Tuff

Cited by 5 publications

References 10 publications

The Analytical Repository Source-Term (AREST) model: Description and documentation

The Analytical Repository Source-Term (AREST) model: Description and documentation

Dry oxidation and fracture of LWR spent fuels

Modeling of thermally driven hydrological processes in partially saturated fractured rock

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