The Water Detritiation System of the ITER Tritium Plant

Iwai, Yasunori; Misaki, Y.; Hayashi, T.; Yamanishi, Toshihiko; Konishi, Satoshi; Nishi, M.; Ninomiya, Rikuo; Yanagimachi, Shinzo; Senrui, S.; Yoshida, Hiroshi

doi:10.13182/fst02-a22759

Cited by 57 publications

(19 citation statements)

References 6 publications

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“…The SPE water electrolyzer is planned to be used in the water detritiation system (WDS) 4) of the ITER, 5) international thermonuclear experimental reactor. Organic polymers are used in the present commercial SPE water electrolyzer as ion exchange membrane, a set of gaskets and electric insulators.…”

Section: Introductionmentioning

confidence: 99%

Durability of Irradiated Polymers in Solid-Polymer-Electrolyte Water Electrolyzer

Iwai¹,

Yamanishi²,

Nishi³

et al. 2005

Journal of Nuclear Science and Technology

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The durability of irradiated organic polymers in solid-polymer-electrolyte water electrolyzer was investigated by gamma-ray irradiation tests around 500 kGy. Serious deteriorations for the tensile strength and ion exchange capacity of the ion exchange membrane (Nafion Ò ) were not observed up to 850 kGy. No serious damage was also observed for tensile strength of the gasket materials (Aflas Ò ) up to 500 kGy. The insulator materials (PFA and FEP) lost their tensile strength at 200 kGy and 300 kGy, respectively. From the above results, we can safely say that the electrolysis cell could be used up to around 500 kGy of irradiation conditions in the case where PFA and FEP are replaced by the polyimide resin which durability against the irradiation is well demonstrated. Two degrading mechanisms were supposed as the effect of irradiation. One is the direct degradation of the chain and branch by gamma-ray. The other is degradation by the attack of radicals. It was demonstrated that the effect of radicals on degradation of the membrane was not dominant. In addition, oxygen was observed to have a large influence on degradation. The quantity of dissolved fluorine in water that could be measured easily was found to correlate closely with tensile strength and ion exchange capacity. Hence, it is possible to evaluate the degradation of ion exchange membrane by monitoring the quantity of dissolved fluorine in water. Concerning the difference of degrading mechanism of the ion exchange membrane due to irradiation source, the combinations of tensile strength, ion exchange capacity and quantity of dissolved fluorine are proposed as deterioration indexes.

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Section: Introductionmentioning

confidence: 99%

Durability of Irradiated Polymers in Solid-Polymer-Electrolyte Water Electrolyzer

Iwai¹,

Yamanishi²,

Nishi³

et al. 2005

Journal of Nuclear Science and Technology

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“…A larger version ofthe process used at the Japanese Fugen reactor has been designed for use with the proposed International Thermonuclear Experimental Reactor (ITER), a fusion reactor (Iwai et al 2002). A significant amount of development work on CECE has been performed to support the ITER, which is being constructed at Cadarache, France with multinational technical participation and funding (Cristescu et al 2007), , (Michling 2008), (Yamanishi 2008).…”

Section: Hto => Ht + 12 Ozmentioning

confidence: 99%

2009 Evaluation of Tritium Removal and Mitigation Technologies for Wastewater Treatment

Kj¹,

Dj²,

Ge³

2009

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“…As shown in Table 2, protium stream with tritium recovered from Hot Cell Atmosphere Detritiation System through Water Detritiation System (WDS) is a load anticipated in all the state. The WDS, 11) utilizing a Combined Electrolysis and Chemical Exchange as a tritium enrichment system, will receive and store tritium contaminated water (up to several GBq/cm 3 ), and processes that in a steady state operation through almost all the operational year, then deliver tritium as tritium enriched protium gas to ISS in a steady state manner. Thus, operations of WDS and ISS are closely combined and also the line of the protium rejection from ISS is connected to the catalytic exchange column of WDS to minimize tritium concentration in the effluent to the environment, and it can be said that the steady state loads introduced from WDS is a ''base load'' to ISS.…”

Section: Steady State Loads To Tritium Plant From Watermentioning

confidence: 99%

Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities

O’hira

Yamanishi

Hayashi

2006

Journal of Nuclear Science and Technology

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Operability and operation scenario of hydrogen Isotope Separation System (ISS) for ITER and a demo reactor are checked and examined based on the information in the ITER documents. It has been confirmed that the current ISS design well covers the operational requirements of the designated operation modes and other anticipated operations. However, some operation modes using rich deuterium fuel will require additional tritium inventory in the system (not only for ISS but the storage system in some cases) and make duration time between the operations longer. Operation scenario of ISS for a demo reactor will be quite simple, but the process capacity required being associated with detritiation of coolant water become excessively large without any countermeasure to control/reduce tritium permeation in the bleeding blanket operated at a temperature much higher than that of ITER.

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The Water Detritiation System of the ITER Tritium Plant

Cited by 57 publications

References 6 publications

Durability of Irradiated Polymers in Solid-Polymer-Electrolyte Water Electrolyzer

Durability of Irradiated Polymers in Solid-Polymer-Electrolyte Water Electrolyzer

2009 Evaluation of Tritium Removal and Mitigation Technologies for Wastewater Treatment

Operation Scenarios and Requirements for Fuel Processing in Future Fusion Reactor Facilities

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