Tritium safety consideration in the design of tritium systems for China HCSB and DFLL TBMs

Chen, C.A.; Luo, Dan; Sun, Ying; Huang, Zhiyong; Xiong, Yi

doi:10.1016/j.fusengdes.2008.07.026

Cited by 16 publications

(3 citation statements)

References 13 publications

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“…We proposes a new TES design on the original design [5] which mainly comprising of a hot metal bed to decompose the HTO vapor arising in the breeder material, a liquid nitrogen cooled molecular sieve bed to adsorb the molecular tritium, and a hydrogen isotope separation subsystem to enrich tritium from the regeneration gas of the MS bed. The layout of the TES is shown in Fig.…”

Section: Update Design Of the Tesmentioning

confidence: 99%

Progress of China's TBM tritium technology

Luo¹,

Song²,

Huang³

et al. 2012

Fusion Engineering and Design

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Section: Update Design Of the Tesmentioning

confidence: 99%

Progress of China's TBM tritium technology

Luo¹,

Song²,

Huang³

et al. 2012

Fusion Engineering and Design

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“…In normal operation, assuming 10% of LiPb flowed into liquid gas contactor (LGC) with an efficiency of 80%, 0.1% of the helium coolant flowed into coolant purification system (CPS) with an efficiency of 95%, the efficiency was 95% for tritium recovery system (TRS)and 99% for vent detritiation system (VDS), and the tritium permeation reduction factor (TPRF) was 1 in the TBM and 100 in the auxiliary system [15], the result of the tritium release into the environment as HT was ∼1.353 mg-T yr −1 , which was much lower than the total TBM annual release limit of 10 mg-T yr −1 as HT, and the tritium permeation inventory into the ITER heat removal system through the TBM He/H 2 O heat exchanger was ∼0.010 mg-T yr −1 as HTO, which was much lower than the total TBM annual release limit, i.e. 1 mg-T yr −1 as HTO [16,17].…”

Section: Tritium Releasementioning

confidence: 99%

Preliminary safety analysis for the Chinese ITER Dual Functional Lithium–Lead Test Blanket Module

Chen¹,

Bai²,

Hu³

et al. 2009

Nucl. Fusion

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Safety analysis is a part of the ITER Test Blanket Module (TBM) design process to ensure that the TBM does not adversely affect the safety of ITER. To get the license for TBM as a whole with International Thermonuclear Experimental Reactor (ITER), the relevant safety analysis is required for each TBM system proposed by each party. The safety analysis for the Chinese Dual-Functional Lithium-Lead Test Blanket Module (DFLL-TBM) has been performed based on the latest DFLL-TBM design. In this paper, the following safety considerations, such as source terms, operational releases, accident sequence analyses and waste assessment, have been analyzed. Both deterministic approach and complementary systematic approach starting with FMEA (Failure Mode and Effects Analysis) studies have been adopted in the accidental analysis. The preliminary resultsshow that the DFLL-TBM system at normal operating conditions and under accident scenarios does not add additional safety hazards to ITER machine and can meet the ITER safety requirement and additional safety requirements for TBM system.

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“…It should be reached in less than 12 h after the plasma shutdown. Tritium management in ITER is one of the main safety engineering issues [4][5][6]. Thus, several researches have been conducted on the tritium inventory and transport in TBM port cells.…”

Section: Introductionmentioning

confidence: 99%

Tritium management in ITER test blanket systems port cell for maintenance operations

Jiang,

Wu,

et al. 2024

Nucl. Fusion

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Four Test Blanket Systems (TBS) will be tested in the International Thermonuclear Experimental Reactor (ITER) equatorial ports #16 and #18 to verify tritium breeding and heat extraction technology. A significant quantity of tritium would be produced in TBM, and partly released into the port cell from the pipework of TBS or other high-temperature components due to its strong mobility and high permeation. The port cell should be accessible during equipment maintenance and human intervention. This work built a multi-dimensional geometric model to characterize HTO transport in the port cell, absorption/desorption, and diffusion in walls and discussed the effect of paint thickness, ventilation rate, source term, and epoxy properties on detritiation efficiency. The results suggest that a 0.1-0.16 mm paint with the lowest HTO solubility is optimal from the compromise between quick cleanup and tritiated waste decommission. A higher ventilation rate could accelerate detritiation while minimizing the radioactive source by a tritium-resisting layer is the most direct method. The optimized design options for reducing the time required to reach 1 DAC in 12 h still need further discussion because of the delayed HTO source from epoxy paint and dead zone of the flow field.

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Tritium safety consideration in the design of tritium systems for China HCSB and DFLL TBMs

Cited by 16 publications

References 13 publications

Progress of China's TBM tritium technology

Progress of China's TBM tritium technology

Preliminary safety analysis for the Chinese ITER Dual Functional Lithium–Lead Test Blanket Module

Tritium management in ITER test blanket systems port cell for maintenance operations

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