Hydrogen transfer in Pb–Li forced convection flow with permeable wall

Fukada, Satoshi; Muneoka, Taiki; Kinjyo, Mao; Yoshimura, Rhosuke; Katayama, Kazunari

doi:10.1016/j.fusengdes.2015.05.017

Cited by 6 publications

(3 citation statements)

References 14 publications

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“…These simulation platforms include customization capabilities, where MHD modules can be integrated into available fluid dynamic solvers. For validation of non-MHD mass transfer in these codes, there are few facilities available where hydrogen isotopes are dissolved in flowing PbLi, as described in [117] or the recently constructed CLIPPER loop [118] at CIEMAT. At ENEA Brasimone, the TRIEX-II facility is able to qualify GLC, PAV and VLC technologies at different temper-atures, PbLi mass flow rates and hydrogen isotopes concentrations [119].…”

Section: Tritium Analysis Methods Transport Modeling and Coupling With Mhdmentioning

confidence: 99%

MHD R&D Activities for Liquid Metal Blankets

et al. 2021

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According to the most recently revised European design strategy for DEMO breeding blankets, mature concepts have been identified that require a reduced technological extrapolation towards DEMO and will be tested in ITER. In order to optimize and finalize the design of test blanket modules, a number of issues have to be better understood that are related to the magnetohydrodynamic (MHD) interactions of the liquid breeder with the strong magnetic field that confines the fusion plasma. The aim of the present paper is to describe the state of the art of the study of MHD effects coupled with other physical phenomena, such as tritium transport, corrosion and heat transfer. Both numerical and experimental approaches are discussed, as well as future requirements to achieve a reliable prediction of these processes in liquid metal blankets.

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Section: Tritium Analysis Methods Transport Modeling and Coupling With Mhdmentioning

confidence: 99%

MHD R&D Activities for Liquid Metal Blankets

et al. 2021

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“…諸言諸言諸言液体鉛リチウム合金(Pb-Li)は、核融合炉の液体トリチウム(T) 増殖材として期待されている。欧州や、中国、インド等では、 ITER-TBM 計画 [1]を含めて、Pb-Li 液体増殖ブランケットの設計や材料共存性等に関する研究が進められている。日本では、原型炉以降の先進ブランケットの概念設計や、レーザー核融合炉の液体壁の研究 [2]、共存性研究 [3]、T 回収研究 [4]等が実施されている。液体ブランケットシステムでは、発生した熱を熱交換器を介して 2 次冷却系統に輸送して発電に用いる。この時、液体ブランケットで生成した T は、1 次系の T 回収器より回収されるが、一部の T は熱交換器の伝熱管を透過して 2 次冷却系以降に輸送される事が懸念される。この T 透過漏洩は、炉内の T 経済 [5]と安全性 [6]に影響する。液体ブランケットの高温化や長寿命化を目指し、溶融 Pb-Li 環境下における鋼材構成元素の溶出型腐食を抑制する耐食被覆の検討も進められている。 T 透過防止膜や耐食膜として、酸化物コーティングが開発されてきた [7]。液体増殖材中の酸素ポテンシャルは極端に低い条件にある為、これらの材料には優れた熱力学的安定性が要求される。候補材料である Er2O3 [3,[8][9][10][11]、Y2O3 [10,11]、ZrO2、 Al2O3 [10]等の共存性が調べられてきた。また、液体金属環境下における Er、Y、Zr、Al 等の金属基盤の酸化機構を応用した自己修復性機能も検討されている [12][13]…”

Section: 諸言unclassified

On-line monitoring of oxygen potential and structure of oxide layer in liquid metals by electrochemical methods

Kondo

Adhi

Takahashi

et al. 2016

The Proceedings of the National Symposium on Power and Energy Systems

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“…The chemical compatibility of the Pb-Li alloy with candidate structural materials [1,2] and the chemical behavior of tritium in the alloy [3,4] are important issues. It is known that the chemical characteristics of liquid metals are determined by the impurities dissolved in the metals.…”

Section: Introductionmentioning

confidence: 99%

Experimental Study on Chemical Behaviors of Non-Metal Impurities in Pb, Pb-Bi and Pb-Li by Temperature Programmed Desorption Mass Spectrometer Analysis

Kondo

Nakajima

Tanaka

et al. 2016

Plasma and Fusion Research

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The chemical behaviors of non-metal impurities such as O 2 , H 2 , N 2 , H 2 O, CO 2 and CO in lead (Pb) metal, lead-bismuth (Pb-Bi) alloy and lead-lithium (Pb-Li) alloys were experimentally investigated by means of temperature programmed desorption mass spectrometer (TPD-MS) analysis. Desorption of H 2 O and CO 2 from the Pb metal and the Pb-Bi alloy was clearly detected by TPD-MS analysis. However, desorption of H 2 O and CO 2 from the Pb-Li alloys was much less than that from the Pb metal and the Pb-Bi alloy, since these molecules are chemically unstable and react with Li in the Pb-Li alloys. Then, oxygen and hydrogen must be dissolved in Pb-Li alloys as they form the chemical compounds of Li (i.e., Li 2 O, LiOH and LiH). Large desorption of hydrogen from solid Pb-Li alloys by their heating was detected. The possible mechanism for the large desorption of hydrogen from the Pb-Li alloys is based on the decomposition of LiH and Pb-Li-H at high temperature. The chemical behaviors of the non-metal impurities in the Pb-Li alloys was modeled based on the thermodynamic stability. The methodologies for the fabrication of high-purity Pb-Li alloys and the control of the impurity condition are discussed.

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Hydrogen transfer in Pb–Li forced convection flow with permeable wall

Cited by 6 publications

References 14 publications

MHD R&D Activities for Liquid Metal Blankets

MHD R&D Activities for Liquid Metal Blankets

On-line monitoring of oxygen potential and structure of oxide layer in liquid metals by electrochemical methods

Experimental Study on Chemical Behaviors of Non-Metal Impurities in Pb, Pb-Bi and Pb-Li by Temperature Programmed Desorption Mass Spectrometer Analysis

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