Status of the ITER Tritium Plant design

Yoshida, Hiroshi; Kveton, O.K.; Koonce, J.; Holland, D.F.; Haange, R.

doi:10.1016/s0920-3796(98)00113-6

Cited by 29 publications

(15 citation statements)

References 6 publications

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“…According to ITER design [15], the impurity stream from VV is disposed to reduce the tritium content by a factor of ∼10 7 before releasing into the atmosphere, thus most of tritium permeation into VV will be reused and the tritium release into environment from VV can be neglected.…”

Section: Analysis Resultsmentioning

confidence: 99%

Analysis on Tritium Management in FLiBe Blanket for LHD-Type Helical Reactor FFHR2

Song

Sagara

Muroga

et al. 2012

Plasma and Fusion Research

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In FFHR2 (LHD-type helical reactor) design, FLiBe has been selected as a self-cooling tritium breeder for low reactivity with oxygen and water and lower conductivity. Considering the fugacity of the tritium, particular care and adequate mitigation measures should be applied for the effectively extracting tritium from breeder and controlling the tritium release to the environment. In this paper, a tritium analysis model of the FLiBe blanket system was developed and the preliminary analysis on tritium permeation and extraction for FLiBe blanket system were done. The results of the analysis showed that it was reasonable to select W alloy as heat exchanger (HX) material, the proportion of FLiBe flow in tritium recover system (TRS) was 0.2, the efficiency of TRS was 0.85 and tritium permeation reduction factor (TPRF) was 20 in blanket etc.. In addition, further R&D efforts were required for FFHR2 tritium system to guarantee the tritium self-sufficient and safety, for example reasonable quality of tritium permeation barriers on blanket, requirement for the TRS and fabrication technology of the heat exchanger etc.. InroductionForce-free helical reactor (FFHR) is a demo-relevant helical-type D-T fusion reactor based on the great amount of R&D results obtained in the LHD project. FLiBe has attractive merits on safety aspects: low tritium solubility, low reactivity with air and water, low pressure operation, and low MHD resistance which is compatible with high magnetic field designs. Thus FLiBe has been selected as a self-cooling tritium breeder in FFHR2 designs [1].Tritium is one of the nuclear fuels and the significant radioactive sources for fusion reactors. Thus the tritium control in a breeding blanket is a key issue in terms of both tritium self-sufficiency and safety of the fusion plant. Considering the fugacity of the tritium and its low solubility in FLiBe, particular care and adequate mitigation measures are to be applied in the FLiBe blanket system in order to keep the tritium release rate to the environment below the allowable level i.e.10 Ci/day [2].In this paper, preliminary sensitive analysis on tritium management in FLiBe blanket of FFHR2 has been done. The factors which affected tritium extraction and permeation were calculated and evaluated, such as the different heat exchanger, proportion of FLiBe flow in tritium recover system (TRS), efficiency of TRS, and tritium perme- ation reduction factor (TPRF) in blanket etc. The analysis results were given, and a conclusion has been made. Analysis Method and Model for Tritium Mass BalanceThe tritium flow model of the entire FFHR2 blanket system was developed, which included the FLiBe blanket and major components of the auxiliary system. A schematic chart of this model was shown in Fig. 1.Based on the tritium flow mode, a simplified tritium analysis model for FLiBe blanket system was developed, and shown in Fig. 2. Utilizing the mass balance theory, an equation can be written as:where M T/FLiBe is the tritium inventory in FLiBe, J 1 is tritium production rate, ...

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Section: Analysis Resultsmentioning

confidence: 99%

Analysis on Tritium Management in FLiBe Blanket for LHD-Type Helical Reactor FFHR2

Song

Sagara

Muroga

et al. 2012

Plasma and Fusion Research

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show abstract

“…According to ITER [25], the impurity stream from VV is disposed to reduce the tritium content by a factor of ∼10 7 before releasing into the atmosphere, thus the tritium release into environment from VV can be neglected.…”

Section: Resultsmentioning

confidence: 99%

Analysis on tritium controlling of the dual-cooled lithium lead blanket for fusion power reactor FDS-II

Song

Huang

Wang

et al. 2009

Fusion Engineering and Design

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“…Effluent gas from ITER confinement buildings is exhausted through the VDS (Vent Detritiation System) for final detritiation before release into the atmosphere [22]. The target annual release of tritium to the environment from a TBM should be ∼1/100th of that for the ITER facility annual limit, which are 1 mg T/year as HTO and 10 mg T/year as HT [21,23].…”

Section: Respectivelymentioning

confidence: 99%