Spent fuel dissolution studies FY 1991 to 1994

Gray, W.J.; Wilson, C.N.

doi:10.2172/205055

Cited by 40 publications

(51 citation statements)

References 20 publications

(31 reference statements)

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“…Several studies have been performed to determine the contribution of the gap and the grain boundaries contribution to IRF [26][27][28][29][30][31][32][33][34][35][36][37]. These studies were mainly focused on caesium, strontium and technetium in UOX [26][27][28]31,32,[35][36][37], MOX [36] and CANDU [29][30][31][32][33][34] fuels. The gap contribution was obtained using cladded fuel segments meanwhile the grain boundary contribution was obtained by using powder samples.…”

Section: Introductionmentioning

confidence: 99%

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

González-Robles

Serrano‐Purroy

Sureda

et al. 2015

Journal of Nuclear Materials

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The denominated instant release fraction (IRF) is considered in performance assessment (PA) exercises to govern the dose that could arise from the repository. A conservative definition of IRF comprises the total inventory of radionuclides located in the gap, fractures, and the grain boundaries and, if present, in the high burn-up structure (HBS). The values calculated from this theoretical approach correspond to an upper limit that likely does not correspond to what it will be expected to be instantaneously released in the real system. Trying to ascertain this IRF from an experimental point of view, static leaching experiments have been carried out with two commercial UO2 spent nuclear fuels (SNF): one from a pressurized water reactor (PWR), labelled PWR, with an average burn-up (BU) of 52 MWd·kgU

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Section: Introductionmentioning

confidence: 99%

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

González-Robles

Serrano‐Purroy

Sureda

et al. 2015

Journal of Nuclear Materials

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“…Thus, the porosity of a waste package is 65%. The specific surface area of spent fuel was set to 39 cm2/g, according to Gray and Wilson (1995). According to the modeling results for the long-term average seepage into drift (Francis et al, 1998), the velocity of water seeping into waste packages is set to 3.2 cdyear, water saturation in waste packages is set to be a constant 70%.…”

Section: Model Configurationsmentioning

confidence: 99%

Using reactive transport modeling to evaluate the source term at Yucca Mountain

Chen

2003

Computers & Geosciences

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“…and to to to For the solubility of Np, we used a range of 1.6 x lo-'' to 3.9 x M with a loguniform probability distribution for the 1997 PA. This range is based on laboratory studies of the reaction of spent fuel or borosilicate glass with simulated Yucca Mountain groundwater under static or flowing conditions by Rai et al (1982), Wilson (1990aWilson ( , 1990b, Wilson and Bruton (1990), Finn et al (1995), and Gray and Wilson (1995). These investigators directly determined the quantities of Np released, or provided information from which the quantities of Np released were calculated assuming congruent dissolution.…”

Section: -36mentioning

confidence: 99%

“…based on the degree of irradiation that will be subject to leaching. A value of 3.96 x10-3 m2/g (Gray and Wilson, 1995) has been recommended as a reasonable minimum surface area for typical spent fuel. A maximum value of 0.1 m2/g (Gray and Wilson, 1995) could be used for severely disrupted fuels such as the TMI debris.…”

Section: -48mentioning

confidence: 99%

Update to Assessment of Direct Disposal in Unsaturated Tuff of Spent Nuclear Fuel and High-Level Waste Owned by U.S. Department of Energy

Wheatley¹,

Rechard²

1998

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The overall purpose of this study is to provide information and ,@dance to the Office of Environmental Management of the U.S. Department of Energy (DOE) about the level of characterization necessary to dispose of DOE-owned spent nuclear fuel (SNF). The disposd option modeled was codisposal of DOE SNF with defense high-level waste (DHLN). A specific goal was to demonstrate the influence of DOE SNF, expected to be minor, in a predominately commercial repository using modeling conditions similar to those currently assumed by the Yucca Mountain Project (YMP). A performance assessment (PA) was chosen as the method of analysis. The performance metric for this analysis (referred to as the 1997 PA) was dose to an individual; the time period of interest was 100,000 yr. Results indicated that cumulative releases of "Tc and 237Np (primary contributors to human dose) fiom commercial SNF exceed those of DOE SNF both on a per MTHM and per package basis. Thus, if commercial SNF can meet regulatory performance criteria for dose to an individual, then the DOE SM; can also meet the criteria. This result is due in large part to lower burnup of the DOE SNF (less time for irradiation) and to the DOE SNF's small percentage of the total activity (1.5%) and mass (3.8%) of waste in the potential repository. Consistent-with the analyses performed for the YMP, the 1997 PA assumed all cladding as failed, which also contributed to the relatively poor performance of commercial SNF compared to DOE SNF.September 30, 1998 i .. PrefaceThis study, the 1997 performance assessment (1997 PA), evaluates whether spent nuclear fuel (SNF) owned by the Office of Environmental Management of the U. S. Department of Energy (DOE) performs noticeably better (or worse) than commercial SNF, and identifies important parameters that influence this performance after disposal. The latter results, in particular, are intended to help define appropriate requirements for waste characterization with regard to DOE-owned SNF being accepted for disposal. The study is part of a broader DOE program, the National Spent Nuclear Fuel Program, for developing a safe, cost-effective technical strategy for the interim management and ultimate disposition of the foreign and domestic spent nuclear fuel under the DOE'S jurisdiction. The DOE-owned SNF is currently stored at three primary sites (Idaho National Engineering and Environmental Laboratory [INEEL], the Hanford reservation, and the Savannah River plant) and several secondary DOE sites. The SNF originated in experimental, defense, and foreign reactors. Organization of ReportThis report is a detailed account of the analysis design and results. The introductory chapter describes the analysis goals and approach, highlights some of the analysis decisions made during the assessment, and sets the stage for the data and concepts that are presented in later chapters. Chapter 2 provides information on the performance measures and assumptions made with regard to modeling style.The remaining chapters cover the tasks of performance...

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Spent fuel dissolution studies FY 1991 to 1994

Cited by 40 publications

References 20 publications

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Dissolution experiments of commercial PWR (52 MWd/kgU) and BWR (53 MWd/kgU) spent nuclear fuel cladded segments in bicarbonate water under oxidizing conditions. Experimental determination of matrix and instant release fraction

Using reactive transport modeling to evaluate the source term at Yucca Mountain

Update to Assessment of Direct Disposal in Unsaturated Tuff of Spent Nuclear Fuel and High-Level Waste Owned by U.S. Department of Energy

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