Tritium recovery from lithium, based on a cold trap

Sze, D.K.; Mattas, R.F.; Anderson, J.L.; Haange, R.; Yoshida, Hiroshi; Kveton, O.K.

doi:10.1016/0920-3796(95)90042-x

Cited by 15 publications

(12 citation statements)

References 4 publications

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“…Liquid metal fission reactors (the Experimental Breeder Reactor II (Holmes, 1977), the Fast Flux Test Facility (McCown, 1980), Hallam and Fermi I (Yevick, 1966), Rapsodie, Phenix, and Super-Phenix plants (Abramson, 1976)) have used cold traps to remove oxide impurities. Recent studies of a liquid lithium system also adopted a cold trap for impurity removal (Sze, 1995;Kato, 1998). Both solid and liquid wall approaches are expected to experience some small level of flow-induced erosion (flow speeds can be high but turbulence should be low, so erosion should be low), radiolytic effects, some level of corrosion, and initial and/or periodic impurities (oxides, etc.)…”

Section: Ex-vessel Pipingmentioning

confidence: 99%

Qualitative Reliability Issues for Solid and Liquid Wall Fusion Design

Cadwallader¹

2001

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This report is an initial effort to identify issues affecting reliability and availability of solid and liquid wall designs for magnetic fusion power plant designs. A qualitative approach has been used to identify the possible failure modes of major system components and their effects on the systems. A general set of design attributes known to affect the service reliability has been examined for the overview solid and liquid wall designs, and some specific features of good first wall design have been discussed and applied to these designs as well. The two generalized designs compare well in regard to these design attributes. The strengths and weaknesses of each design approach are seen in the comparison of specific features.iv SUMMARY Some members of the magnetic fusion community have suggested that conventional solid wall armor for magnetic fusion is not reliable enough to make the overall fusion plant economically attractive, and they have suggested design alternatives such as liquid self-renewing walls. Other members of the magnetic fusion community believe that strides have been made in solid walls and are dubious of the technical feasibility of liquid walls. Such feasibility issues may not be overcome even if the overall availability of liquid wall systems were greater than that of conventional solid walls. A quantitative analysis of the availability of these two approaches cannot be performed because there is inadequate design detail at the present time. A preliminary qualitative examination of the reliability issues associated with solid and liquid walls can be useful to help understand the strengths and weaknesses of each approach, and to highlight areas for further study.This report presents a preliminary examination of qualitative reliability issues of solid wall and liquid wall fusion designs. A comparative failure modes and effects analysis (FMEA) approach was used to identify the different reliability issues for the two design concepts. Very generalized designs were used for the evaluation. Using the results of the FMEA method, the following eight issues of importance were identified: coolant pump reliability, vacuum quality, liquid wall nozzle reliability, maintenance downtime issues, responses to loss of vacuum accidents (that is, vacuum component failures), responses to loss of coolant accidents (that is, piping failures), helium pumping ability for vacuum cleanliness, and natural circulation of reactor coolant.

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Section: Ex-vessel Pipingmentioning

confidence: 99%

Qualitative Reliability Issues for Solid and Liquid Wall Fusion Design

Cadwallader¹

2001

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“…The tritium recovery process proposed here is based on cold trap process [6]. The cold trap process has been demonstrated to be able to recover tritium from lithium [7], sodium [8] and potassium [9] to their solubility limits.…”

Section: Tritium System Descriptionmentioning

confidence: 99%

“…The development of the insulating coating is still in an early stage and much further work needs to be done. 6. Tritium recovery To recover tritium from lithium to a very low concentration (-1 appm) is very difficult.…”

Section: Insulatinrr Coating Developmentmentioning

confidence: 99%

The ARIES-RS power core—recent development in Li/V designs

Sze

Billone

Hua

et al. 1998

Fusion Engineering and Design

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The ARIES-RS fusion power plant design study is based on reversed-shear (RS) physics with a LiN (lithium breeder and vanadium structure) blanket. The reversed-shear discharge has been documented in many large tokamak experiments. The plasma in the RS mode has a high beta, low current, and low current drive requirement. Therefore, it is an attractive physics regime for a fusion power plant. The blanket system based on a LiN has high temperature operating capability, good tritium breeding, excellent high heat flux removal capability, long structural life time, low activation, low after heat and good safety characteristics. For these reasons, the ARES-RS reactor study selected W as the reference blanket. The combination of attractive physics and attractive blanket engineering is expected to result in a superior power plant design. This paper summarizes the power core design of the ARIES-RS power plant study.

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“…The tritium recovery method proposed here is based on the cold trap process [3]. The cold trap process has been demonstrated to recover tritium from lithium [4], sodium [5], and potassium [6] to their solubility limits.…”

Section: Tritium Handling and Processing Subsystemmentioning

confidence: 99%

Tritium processing system for the ITER Li/V Blanket Test Module

Sze

Hua

Dagher

et al. 1998

Fusion Engineering and Design

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The purpose of the ITER Blanket Testing Module is to test the operating and performance of candidate blanket concepts under a real fusion environment. To assure fuel self-sufficiency, the tritium breeding, recovery and processing have to be demonstrated. The tritium produced in the blanket has to be processed to a purity which can be used for refuelling. All these functions need to be accomplished so that the tritium system can be scaled to a commercial fusion power plant from a safety and reliability point of view. This paper summarizes the tritium processing steps, the size of the equipment, power requirements, space requirements, etc. for a self-cooled lithium blanket. This information is needed for the design and layout of the test blanket ancillary system and to assure that the ITER guidelines for remote handling of ancillary equipment can be met.

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Tritium recovery from lithium, based on a cold trap

Cited by 15 publications

References 4 publications

Qualitative Reliability Issues for Solid and Liquid Wall Fusion Design

Qualitative Reliability Issues for Solid and Liquid Wall Fusion Design

The ARIES-RS power core—recent development in Li/V designs

Tritium processing system for the ITER Li/V Blanket Test Module

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