Performance of exhaust detritiation system for a fusion test device in the initial phase of the operation

Tanaka, Masahiro; Suzuki, Naoyuki; Kato, Hiromi; Chimura, Hiroki

doi:10.1016/j.fusengdes.2020.112172

Cited by 4 publications

(2 citation statements)

References 18 publications

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“…It is assumed that there is no tritiated water in the experimental hall at the beginning and that tritium is released as hydrogen. A conversion rate of tritium to tritiated water and a removal rate of tritiated water are assumed to be 0.990 [44] and 0.999% [45], respectively, from past achievements. Figure 13 shows trends of tritium concentration on circulation flow rates: 2000, 3000, and 4100 Nm 3 h −1 in an experimental hall of 20 000 m 3 .…”

Section: Emergency Operationmentioning

confidence: 99%

Baseline design of laser fusion research reactor with MW class laser facility

Iwamoto,

Tanaka,

Shigemori

et al. 2024

Nucl. Fusion

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We propose a sub-ignition/burning reactor which is named the Laser-fusion Subcritical Power Reactor Engineering Method (L-Supreme). The reliabilities of L-Supreme in a MW class laser facility are assessed with respect to the following points: a reactor core, a target chamber, a target delivery system, an Exhaust Detritiation System (EDS), and neutron shielding. The Japan Establishment for Power-laser Community Harvest (J-EPoCH) would be applied as a MW class laser facility. A non-cryogenic glass balloon target filled with gaseous deuterium-tritium (DT) is contained in a target capsule. A chain-type magazine system might be used for a mass supply of the target capsules. Each target capsule is delivered to the center of a reactor core at 1 Hz. A batch of 10000 laser shots would realize 0.22 MJ fusion power. The amount of tritium per batch is 1.51 x 1012 Bq. During laser experiments, unburned tritium is evacuated and transferred into an Exhaust Detritiation System (EDS). An evacuation rate of more than 0.1 m3/s is required in order to recover less than 5000 Bq/m3 of the threshold of tritium concentration within one hour. For safety, emergency situations such as tritium leakage in facilities are examined. The EDS works by internal circulation processes. Assuming leakage of tritium for a batch, an air circulation flow rate of 4100 Nm3/h is required in an experimental hall for recovering less than 5000 Bq/m3 within 48 hours. A primary and secondary neutron shield concept are proposed and would provide full neutron shielding. We conclude that it is possible to construct the L-Supreme system by marshalling current technologies.

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Section: Emergency Operationmentioning

confidence: 99%

Baseline design of laser fusion research reactor with MW class laser facility

Iwamoto,

Tanaka,

Shigemori

et al. 2024

Nucl. Fusion

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“…Thus, it would be essential to decontaminate the molecular sieve to be lower the tritium inventory in the MS system. For the decontamination of molecular sieves, the isotope swapping method using water vapor (H2O) has been carried out [19] and was effective for decontaminating tritium in absorbent materials.…”

Section: The Estimation Of Tritium Inventory and Balance In Edsmentioning

confidence: 99%