Compatibility between SiC and Li ceramics for solid breeding blanket system

Nogami, Shuhei; Hasegawa, Akira; Murayama, Takahide; Otake, N.; Satou, Mamoru; Abe, Katsunori

doi:10.1016/j.jnucmat.2008.12.225

Cited by 13 publications

(6 citation statements)

References 5 publications

(11 reference statements)

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“…Silicon carbide possesses physical and chemical properties that make it a promising material for many uses, not only for advanced electronic devices (Raynaud 2001) but also for structural components in fusion reactors (Fenici et al 1998;Nogami et al 2009;Zhao et al 2007;Wong et al 2007;Katoh et al 2007), as a barrier for fission product diffusion in gas-cooled fission reactors (Kim et al 2000), and as an inert matrix for the transmutation of plutonium and other transuranics (Verrall et al 1999;Krstić et al 1996). The high thermal conductivity of SiC also enhances homogeneous heat distribution that facilitates the dissipation of radiodecay heat.…”

Section: Waste Formsmentioning

confidence: 99%

Assessments and Options for Removal and Immobilization of Volatile Radionuclides from the Processing of Used Nuclear Fuel

Jubin

Strachan

2015

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Nuclear fuel reprocessing is being considered in the US as part of an effort to help meet the nation's energy needs. Various options are available to meet these needs (DOE 2010). The recent Fuel Options Study indicated that fuel cycles that utilize continuous recycling are among the "most promising" (Wigeland et al. 2014). After the valuable components have been extracted from the irradiated UO 2 during reprocessing, the remaining waste must be immobilized and sent to a repository. Some of the radionuclides in the fuel are short-lived isotopes that decay to innocuous levels soon after reactor discharge, e.g., 127 Xe (t 1/2 = 36.4 d). However, the preponderance of radionuclides requires long-term, geological storage. In this report, we assess options for capturing and immobilizing radionuclides expected to volatilize during aqueous reprocessing of used nuclear fuel. This document is an update to a previous report prepared in 2011 that was only released as a draft (FCR&D-SWF-2011-000305). Several radionuclides that require intermediate-to long-term storage become volatile during the processing of the fuel. These include 3 H, 14 C, 85 Kr, and 129 I. These radionuclides are released into the gas streams associated with processing the nuclear fuel and are particularly difficult to remove because of their chemical state and very low concentrations. The SCALE code version 6.0 (ORNL 2009) was used to calculate the masses and activities of these volatile radionuclides in representative used commercial light water reactor (LWR) fuels that could be reprocessed for recycling. Two levels of fuel burnup, 30 GWd/tIHM (gigawatt-days per metric ton initial heavy metal) and 60 GWd/tIHM with 5-and 30-year cooling periods (time out of reactor) were selected as reference cases for the these SCALE calculations. A number of the capture methods are reviewed in this study. Although many appear promising, significant research and development remains to be completed to advance them from the laboratory or bench scale to a level suitable for use in commercial facilities. Likewise, significant development and performance testing is needed for waste forms, particularly for iodine. Assessments and Options for Removal and Immobilization of Volatile Radionuclides from the Processing of Used Nuclear Fuel iv 3/31/15 ACKNOWLEDGMENTS The primary authors of this report wish to acknowledge the many researchers at the DOE national laboratories who are part of the Off-Gas Sigma Team and who have contributed information in support of his study. This includes S.

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Section: Waste Formsmentioning

confidence: 99%

Assessments and Options for Removal and Immobilization of Volatile Radionuclides from the Processing of Used Nuclear Fuel

Jubin

Strachan

2015

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“…Other candidate is silicon carbide (SiC) [38], although its integrity at temperatures in the range that is proposed for our loop must be investigated. There is some work already done regarding Pb-Li compatibility with SiC [39], but its application to lithium flows has been scarcely investigated.…”

Section: Conceptual Design Of the Laboratorymentioning

confidence: 99%

Conceptual design of the liquid metal laboratory of the TECHNOFUSION facility

Abánades

García

Casal

et al. 2012

Fusion Engineering and Design

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The application of liquid metal technology in fusion devices requires R&D related to many phenomena: interaction between liquid metals and structural material as corrosion, erosion and passivation techniques; magneto-hydrodynamics; free surface fluid-dynamics and any other physical aspect that will be needed for their safe reliable operation. In particular, there is a significant shortage of experimental facilities dedicated to the development of the lithium technology. In the framework of the TECHNOFU-SION project, an experimental laboratory devoted to the lithium technology development is proposed, in order to shed some light in the path to IFMIF and the design of chamber's first wall and divertors. The conceptual design foresee a development in two stages, the first one consisting on a material testing loop. The second stage proposes the construction of a mock-up of the IFMIF target that will allow to assess the behaviour of a free-surface lithium target under vacuum conditions. In this paper, such conceptual design is addressed.

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“…Silicon carbide possesses excellent physical and chemical properties that make it a promising material, not only for advanced electronic devices (Raynaud 2001), but also for structural components in fusion reactors (Fenici et al 1998;Nogami et al 2009;Zhao et al 2007;Wong et al 2007;Katoh et al 2007), a barrier for fission product diffusion in gas-cooled fission reactors (Kim et al 2000), and an inert matrix for the transmutation of plutonium and other transuranics (Verrall et al 1999;Krstic et al 1996). The high thermal conductivity of SiC also enhances homogeneous heat distribution in devices and rapid heat transfer.…”

Section: Introductionmentioning

confidence: 99%

Summary Report on the Volatile Radionuclide and Immobilization Research for FY2011 at PNNL

Strachan¹,

Chun²,

Matyáš³

et al. 2011

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SUMMARYMaterials were developed and tested in support of the U.S. Department of Energy, Office of Nuclear Energy, Fuel Cycle Technology Separations and Waste Forms Campaign. Specifically, materials are being developed for the removal and immobilization of iodine and krypton from gaseous products of nuclear fuel reprocessing unit operations.During FY 2011, aerogel materials were investigated for removal and immobilization of 129 I. Two aerogel formulations were investigated, one based on functionalized silica and the second on chalcogenbased glasses (i.e., chalcogels). A silica aerogel was tested at ORNL for total I 2 sorption capacity. It was determined to have 48 mass% capacity while having little physisorbed I 2 (I 2 not chemically bound within the aerogel). Metal organic framework (MOF) structures were investigated for the removal and storage of Kr and a new MOF with about 8 mass% capacity for Xe and Kr was formulated and tested. The selectivity can be changed from Xe > Kr to Xe < Kr simply by changing the temperature. A patent disclosure has been filed. Lastly, silicon carbide (SiC) was loaded with Kr. The diffusion of Kr in SiC was found to be less than detectable values at temperatures as high as 500°C.

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Compatibility between SiC and Li ceramics for solid breeding blanket system

Cited by 13 publications

References 5 publications

Assessments and Options for Removal and Immobilization of Volatile Radionuclides from the Processing of Used Nuclear Fuel

Assessments and Options for Removal and Immobilization of Volatile Radionuclides from the Processing of Used Nuclear Fuel

Conceptual design of the liquid metal laboratory of the TECHNOFUSION facility

Summary Report on the Volatile Radionuclide and Immobilization Research for FY2011 at PNNL

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