TY - JOUR
T1 - Analysis of peak heat load on the blanket module for JA DEMO
AU - The Joint Special Design Team for Fusion DEMO
AU - Miyoshi, Yuya
AU - Hiwatari, Ryoji
AU - Someya, Youji
AU - Tokunaga, Shinsuke
AU - Homma, Yuki
AU - Asakura, Nobuyuki
AU - Sakamoto, Yoshiteru
AU - Tobita, Kenji
N1 - Funding Information:
This work was carried out within the framework of the Broader Approach DEMO design Activity. Contribution by all members of JA and EU Home Teams for BA is greatly appreciated. This work also has been supported by a grant-in-aid for Joint Special Design Team for Fusion DEMO from the Ministry of Education, Culture, Sports, Science and Technology .
Funding Information:
This work was carried out within the framework of the Broader Approach DEMO design Activity. Contribution by all members of JA and EU Home Teams for BA is greatly appreciated. This work also has been supported by a grant-in-aid for Joint Special Design Team for Fusion DEMO from the Ministry of Education, Culture, Sports, Science and Technology.
Publisher Copyright:
© 2019 Elsevier B.V.
PY - 2020/2
Y1 - 2020/2
N2 - Plasma heat flux in the peripheral plasma reaches the first wall (FW) along a magnetic field line, and it sometimes causes several MW/m2 orders of magnitude high heat flux concentration at narrow region, such as the edge of the blanket module. Thus, to assess and to reduce the heat load is key issue in the DEMO design activity. In this research, a new heat load analysis code is introduced based on the e-folding model. In this code, the decay length λ is changed depending on wall connection length of magnetic field line (defined as the length of magnetic field line from the wall to the wall), and parallel heat flux q// is calculated in each flux tube. This code can calculate the FW heat load simulating actual blanket module shapes. The 0.23 MW/m2 peak heat load at inner midplane in the case of the ideal FW (without gaps between blanket modules) is increased to 22 MW/m2 at toroidal module edge in the case of box shaped module. To shadow the edge and reduce such peak heat load, toroidal, and poloidal roof shaping is applied. Required roof height is analyzed from this code calculation. After shaping, peak heat load is reduced to 1.2 MW/m2. This value is under the allowable value 1.5 MW/m2, and in this case, surface temperature is also less than allowable temperature.
AB - Plasma heat flux in the peripheral plasma reaches the first wall (FW) along a magnetic field line, and it sometimes causes several MW/m2 orders of magnitude high heat flux concentration at narrow region, such as the edge of the blanket module. Thus, to assess and to reduce the heat load is key issue in the DEMO design activity. In this research, a new heat load analysis code is introduced based on the e-folding model. In this code, the decay length λ is changed depending on wall connection length of magnetic field line (defined as the length of magnetic field line from the wall to the wall), and parallel heat flux q// is calculated in each flux tube. This code can calculate the FW heat load simulating actual blanket module shapes. The 0.23 MW/m2 peak heat load at inner midplane in the case of the ideal FW (without gaps between blanket modules) is increased to 22 MW/m2 at toroidal module edge in the case of box shaped module. To shadow the edge and reduce such peak heat load, toroidal, and poloidal roof shaping is applied. Required roof height is analyzed from this code calculation. After shaping, peak heat load is reduced to 1.2 MW/m2. This value is under the allowable value 1.5 MW/m2, and in this case, surface temperature is also less than allowable temperature.
KW - DEMO
KW - Fusion reactor design
KW - Module shaping
KW - Plasma heat load
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U2 - 10.1016/j.fusengdes.2019.111394
DO - 10.1016/j.fusengdes.2019.111394
M3 - Article
AN - SCOPUS:85075376752
SN - 0920-3796
VL - 151
JO - Fusion Engineering and Design
JF - Fusion Engineering and Design
M1 - 111394
ER -