Table of Content

15 September 2006, Volume 26 Issue 3

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Design of the Chinese ITER helium cooled solid breeder test blanket module

Overview of the ITER test blanket module program

FENG Kai-ming

2006, 26(3):  161-169. 

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In this paper, the ITER project, the ITER test blanket module (TBM) program and its origin are introduced briefly. The definition and development strategy of DEMO reactor, relevant to the TBM program, are summarized. The design progress and R&D plans of Chinese ITER test blanket module design based on the solid breeder concept are also presented.

Calculations of the 3-D neutronics for CH HCSB TBM with 3×3 sub-modules

ZHANG Guo-shu, FENG Kai-ming, CHEN Rong-guang, YUAN Tao, LI Zeng-qiang

2006, 26(3):  170-175. 

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Using three dimension MCNP code and FENDL2.0 data library, neutronics calculation for a HCSB (helium cooling solid breeder ) TBM ( test blanket module ) with 3×3 sub-modules has been performed. Local tritium breeding ratio (TBR) of 0.907, total tritium generation rate of 0.0175 g•d^-1, peak power density of 9.27MW•m^-3  and total power deposit of 0.422MW•m^-3  are obtained under neutron wall loading of 0.78MW•m^-2  and duty factor of 22%.

Activation and afterheat analysis for CH HCSB TBM

CHEN Zhi，FENG Kai-ming，ZHANG Guo-shu，YUAN Tao

2006, 26(3):  176-180. 

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With an activation calculation code FDKR and decay chain data library AF-DCDLIB, the radioactivity, afterheat decay and Biological Hazard Potential (BHP) from activation products have been analyzed in the CH HCSB TBM. The calculation results show that the total radioactivity inventory, heat decay and BHP are 2.10×10¹⁶Bq、5.06×10^-3 MW、68.6 km³•(kW)^-1, respectively, at shutdown after a continuous irradiation over 0.53 years with 500 MW fusion power. It shows that there isn’t seriously environmental safety issue in the TBM.

Thermal hydraulic and mechanical analysis of CH HCSB TBM

WANG Xiao-yu, FENG Kai-ming, ZHANG Guo-shu, YUAN Tao

2006, 26(3):  181-185. 

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Based on the structure design and results of neutronics analysis of the CH HCSB TBM (Chinese helium cooled solid breeder test blanket module), thermal hydraulic and mechanical analyses have been carried out. Results show that the design of the CH HCSB TBM is reasonable and acceptable.

Thermo-hydraulic analysis for sub-module of Chinese HCSB TBM design

ZHAO Zhou, FENG Kai-ming, WANG Xiao-yu, YUAN Tao

2006, 26(3):  186-189. 

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Thermo-hydraulic calculation and analysis for sub-module of Chinese HCSB TBM were carried out using FE code ANSYS. Results indicate that temperature distribution in materials used in sub-module is reasonable and acceptable.

Conceptual design and calculation for fusion neutron diagnostic in NT-TBM

YANG Jin-wei, FENG Kai-ming, CHEN Zhi, YANG Qing-wei

2006, 26(3):  190-194. 

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Neutron measurement system should be able to provide neutron fluxes and spectra at beryllium multiplier and tritium breeder of the neutronics and ttritium production test blanket module (NT-TBM) during D-D and D-T phases in ITER. A special neutron diagnostic system has been proposed for measuring the neutron fluxes and spectra without interrupt to ITER operation. This system includes encapsulated foil activation system, micro-fission chamber detectors (MFC), and a compact neutron spectrometer as natural diamond detector (NDD).

Preliminary structure design of helium cooled solid breeder test blanket module for ITER test blanket programme

YUAN Tao, FENG Kai-ming, WANG Xiao-yu, CHEN Zhi

2006, 26(3):  195-200. 

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Detailed scheme of structure design of ITER helium cooled solid breeder (HCSB) test blanket module (TBM) has carried out. The peculiarity of HCSB TBM is to select the reduced activation ferritic steel (RAFS) as structural material, the high stabilizing helium as coolant, ceramic Li4SiO4 pebble as tritium breeder. In particular, modular structure design of HCSB could enhance the reliability and safety of blanket structure.

The neutron calculation of the Chinese helium cooled solid breeder test blanket module

LI Zeng-qiang，FENG Kai-ming，ZHANG Guo-shu，YUAN Tao

2006, 26(3):  201-204. 

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Based on the ITER CH HCSB 3×3 TBM module, the tritium generation, energy distributing and neutron flux of the CH HCSB TBM have been investigated by one-dimensional neutronics transport computational code ONEDANT and two-dimensional neutronics transport computational code TWODANT. The results are analyzed and compared.

Electromagnetic safety analysis during major disruption

GAO Chun-ming, CHEN Zhi, FENG Kai-ming, WANG Ya-fei

2006, 26(3):  205-209. 

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The electromagnetic safety analysis during major disruption is important for safety analysis of the CH HCSB TBM. In this paper, using finite element method, the electromagnetic safety analysis of the CH HCSB TBM is carried out in consideration of major disruption. First, the finite element models of the CH HCSB TBM and its sub-module are established; second, the distributions of the induced eddy currents and electromagnetic forces on the whole CH HCSB TBM module and its sub-module are calculated; third, the torquemoment on whole CH HCSB TBM module and its sub-module are calculated from the distributions of the electromagnetic forces. Comparing the maximum allowable values of the parameters of the materials with the calculated data, the electromagnetic safety of the CH HCSB TBM is investigated.

Ceramic breeder pebbles for CH HCSB test blanket module

CHEN Xiao-jun, WANG He-yi, LUO Yang-ming, FENG Kai-ming, WEN Zhao-yin

2006, 26(3):  210-216. 

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The function requirements for the solid ceramic breeder used in the CH HCSB test blanket module (TBM) were described. Lithium orthosilicate (Li₄SiO₄) is considered as first candidate material. Fabrication method of the Li4SiO4 powder, its pebble fabrication process and the properties of the Li₄SiO₄ pebbles, such as tritium release and compatibility, were reviewed briefly. Some studies on the tritium breeder in China were also given.

Design of tritium systems for CH HCSB TBM

LUO De-li, CHEN Chang-an, HUANG Zhi-yong, LIU Cong-xian, XIONG Yi-fu, SHI Yan, LEI Qiang-hua, HU Gang

2006, 26(3):  217-222. 

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The ancillary tritium systems, including tritium extract system (TES), coolant purification system (CPS) and tritium measurement system (TMS)， have been designed based on the structure features of Chinese helium cooled solid breeder test blanket module (CH HCSB TBM) for ITER. Functions, technical parameters, and technological processes of these systems have been described. TES is designed to extract tritium produced in the breeder, to store and separate hydrogen isotope gases. Impurities and tritium in the helium coolant are removed through CPS. TMS has the function of testing the tritium breeding rate in TBM and can replace TES sometimes. Tritium release to the environment from CH HCSB TBM is well controlled below the tritium safety limit of ITER, according to the tritium permeation and tritium safety analysis.

Loss of coolant accident analysis for China HCSB TBM

ZHOU Zhi-wei, JIE Heng, YANG Yong-wei, JING Xing-qing, XIAO Jian-jun, JIA Xiao-bo, FENG Kai-ming, CHEN Zhi

2006, 26(3):  223-227. 

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The general-purpose CFD code FLUENT is used to calculate the transient process of China helium-cooled solid breeder test blanket module (TBM) under loss of coolant accident (LOCA) scenario. A 1-D flow discharge model for coolant blow-down and 1-D heat transfer model for afterheat removal aiming at TBM LOCA analysis are developed. The results of typical LOCA analysis show that the contribution of either the TBM relevant events induced or other ITER component events induced TBM accidents to the total ITER safety risk is negligible.

Basic design of fusion neutron diagnostic in ITER NT-TBM

YANG Jin-wei, FENG Kai-ming, CHEN Zhi, YANG Qing-wei

2006, 26(3):  228-232. 

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A basic design of neutron fluxes and spectra diagnostic at beryllium multiplier and tritium breeder in neutronics and tritium production test blanket module (NT-TBM) during D-D and D-T phases in ITER is proposed. This is important for studying and assessing capabilities of beryllium multiplier and tritium breeder in the NT-TBM of China helium cooled solid breeder (CH HCSB). This system includes encapsulated foil activation sub-system, micro-fission chamber detector (MFC) assembly, and a compact neutron spectrometer as natural diamond detector (NDD).

1-D neutronics optimization design for ITER CH HCSB TBM

LI Zeng-qiang, FENG Kai-ming, ZHANG Guo-shu

2006, 26(3):  233-238. 

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The neutronics problem of the TBM module design connects closely with TBM’s other problems, such as, tritium generation, thermo-hydraulic, safety, etc. An exact neutronics calculation for the TBM module is very important. Based on the 1-D calculation model given in the CH HCSB TBM design, a better 1-D neutronics optimization has been performed using the ONEDANT code with related database.

Research papers

The effect of merit functions on fast identification of plasma boundary with the filament current method

LIU Li, YUAN Bao-shan

2006, 26(3):  239-245. 

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The plasma boundary can be identified by filament current method with the magnetic signals from probes around the plasma. The principle of this method is presented and the effects of merit functions on fast identification of plasma boundary are given.

A chopper-stabilized long pulse integrator with low drift

WEI Yong-qing, XIE Ji-kang, WAN Bao-nian, SHEN Biao

2006, 26(3):  246-251. 

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A chopper-stabilized integrator for tokamak with a digital signal processing unit to dynamically suppress the primary drift factors of analog integrator, has been designed. Long pulse integrations with low drift have been obtained with this apparatus in experiments.

Mass spectrometric measurements of SiCl_n(n=0~2) spatial distribution in SiCl₄ plasma

WANG Zhao-kui, LIN Kui-xun, LOU Yan-hui, LIN Xuan-ying, ZHU Zu-song

2006, 26(3):  252-256. 

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A movable gas sampling apparatus located in a rf glow discharge chamber is connected to a mass spectrometer for measuring the spatial distribution of neutral radical in SiCl₄ plasma. A straight-line fit method is used to obtain the plasma depletion fraction, which is a key parameter for deducing the neutral radical density from the mass spectroscopic signals. The experimental results demonstrate that the proposed straight-line fit method is more accurate for deducing the plasma depletion fraction than the previous one, and the movable gas sampling apparatus is suitable for measuring the neutral radicals spatial distribution.