Spent nuclear fuel as a waste form for geologic disposal: Assessment and recommendations on data and modeling needs

Luik, Abraham Van; Apted, M.J.; Bailey, W.J.; Haberman, J.H.; Shade, J.S.; Guenther, R.; Serne, R. Jeffrey; Gilbert, E.R.; Peters, Robert W.; Williford, Rick E.

doi:10.2172/60424

Cited by 5 publications

(6 citation statements)

References 6 publications

(12 reference statements)

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“…Assuming that uranium dissolution obeys a simple concentration dependence as described in Eq. (3), adopting uranium solubilities ranging from 2 x 10~2 g/m 3 at pH 11 to 2 x 10~8 g/m 3 at pH 6, 19 and for other parameters the same as used in the above example for silica, we obtain an estimated flux ratio for the spent-fuel matrix of 5 x 10 4 to 5 x 10 5 , greater by one to seven orders of magnitude than that estimated for silica from borosilicate glass. If these data are correct, uranium dissolution in a geologic repository is likely to be controlled by exterior-field mass transfer and not by chemical reaction rate.…”

Section: >W~) = T I S (5)mentioning

confidence: 88%

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Near-Field Mass Transfer in Geologic Disposal Systems: a Review

Pigford

1987

MRS Proc.

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A primary purpose of performance assessment of geologic repositories for radioactive waste is to predict thr extent to which radioactive species are released from the waste solids and are transported through geologic media to the environment. Reliable quantitative predictions must be made of rates of release of radionuclides from the waste into the rock, transport through the geologic media, cumulative release to the accessible environment, and maximum concentrations in ground water and surface water. Here we review theoretical approaches to making the predictions of near-field release from buried waste solids, which provide the source terms for far-field release. The extent to which approaches and issues depend on the rock media and on regulatory criteria is discussed.

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Section: >W~) = T I S (5)mentioning

confidence: 88%

“…19 list values of jo for unirradiated and irradiated UO2 in deionized water and in brine at various temperatures. They adopt a conservatively low value of j 0 = 0.005 g/m 2 day.…”

Section: >W~) = T I S (5)mentioning

confidence: 99%

Near-Field Mass Transfer in Geologic Disposal Systems: a Review

Pigford

1987

MRS Proc.

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“…14 A model for dissolution is used in which the dissolution front propagates linearly in time, much like a recently published model for the advance of the oxidation front during oxidation Of UO 2 and spent fuel. [16][17][18][19] This implies that the particle geometry is retained. We can describe the change in characteristic dimension of a SF particle (a sort of "radius"), X as follows:…”

Section: Discussionmentioning

confidence: 99%

Waste form characteristics report, revision 1.3

Leider¹,

Stout²

1998

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“…The role and importance of redox reactions in determining actinide mobility and solubility are beyond question (Van Luik et al 1987;Allard 1982;Choppin and Rao 1992). The redox potentials for the various oxidation states at pH 7 are (Cleveland 1979, pp.…”

Section: Importance Of Redox For Plutonium Speciationmentioning

confidence: 99%

Appendix SOTERM-2009 Actinide Chemistry Source Term

Borkowski

Garner²,

Lucchini

et al. 2013

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β (apparent) stability constant, or beta particle Bq becquerel BRAGFLO Brine and Gas Flow code CAPHUM maximum (cap) concentration of actinide associated with mobile humic colloids CAPMIC maximum concentrations of actinides that could be associated with microbes CBFO (U.S. Department of Energy) Carlsbad Field Office CCA Compliance Certification Application Ci Curie cm-1 per centimeter CN coordination number coll colloid conc concentration CONCINT concentration of actinide associated with mobile actinide intrinsic colloids CONCMIN concentration of actinide associated with mobile mineral fragment colloids CPR cellulosic, plastic, and rubber C Pu maximum concentration of all combined isotopes of Pu Cr or c crystalline phase CRA Compliance Recertification Application DBR direct brine release D-H Debye-Hückel theory DOE U.S. Department of Energy DRZ disturbed rock zone E 0 or E 0 redox potential EDS energy dispersive x-ray spectroscopy-Acetate anion (CH 2 CO 2) 2 C(OH)(CO 2) 3-Citrate anion (CH 2 CO 2) 2 N(CH2) 2 N(CH 2 CO 2) 2 4-Ethylenediaminetetraacetate (EDTA) anion C 2 O 4 2

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Spent nuclear fuel as a waste form for geologic disposal: Assessment and recommendations on data and modeling needs

Cited by 5 publications

References 6 publications

Near-Field Mass Transfer in Geologic Disposal Systems: a Review

Near-Field Mass Transfer in Geologic Disposal Systems: a Review

Waste form characteristics report, revision 1.3

Appendix SOTERM-2009 Actinide Chemistry Source Term

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