ログイン
言語:

WEKO3

  • トップ
  • ランキング
To
lat lon distance
To

Field does not validate



インデックスリンク

インデックスツリー

メールアドレスを入力してください。

WEKO

One fine body…

WEKO

One fine body…

アイテム

  1. 原著論文

Development and Application of SONIC Divertor Simulation Code to Power Exhaust Design of Japanese DEMO Divertor

https://repo.qst.go.jp/records/86146
https://repo.qst.go.jp/records/86146
bd61fe92-77cc-4590-9ec1-aa30ebb9be49
Item type 学術雑誌論文 / Journal Article(1)
公開日 2022-05-18
タイトル
タイトル Development and Application of SONIC Divertor Simulation Code to Power Exhaust Design of Japanese DEMO Divertor
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_6501
資源タイプ journal article
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 Nobuyuki, Asakura

× Nobuyuki, Asakura

WEKO 1052213

Nobuyuki, Asakura

Search repository
Hoshino, Kazuo (Keio Univ.)

× Hoshino, Kazuo (Keio Univ.)

WEKO 1052214

Hoshino, Kazuo (Keio Univ.)

Search repository
Yuuki, Homma

× Yuuki, Homma

WEKO 1052215

Yuuki, Homma

Search repository
Yoshiteru, Sakamoto

× Yoshiteru, Sakamoto

WEKO 1052216

Yoshiteru, Sakamoto

Search repository
Special Design Team for Fusion DEMO, Joint

× Special Design Team for Fusion DEMO, Joint

WEKO 1052217

Special Design Team for Fusion DEMO, Joint

Search repository
Nobuyuki, Asakura

× Nobuyuki, Asakura

WEKO 1052218

en Nobuyuki, Asakura

Search repository
Yuuki, Homma

× Yuuki, Homma

WEKO 1052219

en Yuuki, Homma

Search repository
Yoshiteru, Sakamoto

× Yoshiteru, Sakamoto

WEKO 1052220

en Yoshiteru, Sakamoto

Search repository
抄録
内容記述タイプ Abstract
内容記述 An integrated divertor simulation code, SONIC, has been developed in order to predict a self-consistent transport solution of the plasma, neutral and impurities in the scrape-off layer (SOL) and divertor. SONIC code has contributed to determining the divertor design and power handling scenarios for the Japanese (JA) fusion demonstration (DEMO) reactor. Radiative cooling scenario of Ar impurity seeding and the divertor performance have been demonstrated to evalu-ate the power exhaust scenarios with Psep = 230–290 MW. The simulation identified the decay length of the total parallel heat flux profile as being broader than the electron one, because of the ion convective transport from the outer divertor to the upstream SOL, produced by the plasma flow reversal. The flow reversal also reduced the impurity retention in the outer divertor, which may produce the partial detachment. Divertor operation margin of key power exhaust parameters to satisfy the peak qtarget less than 10 MWm−2 was determined in the low nesep of 2 − 3 × 1019 m−3 under severe conditions such as reducing radiation loss fraction, i.e., f*raddiv = (Pradsol + Praddiv)/Psep and diffu-sion coefficients (chi and D). The divertor geometry and reference parameters (f*raddiv ~ 0.8, chi = 1 m2s−1, D = 0.3 m2s−1) were consistent with the low nesep operation of the JA DEMO concepts. For either severe assumption of f*raddiv ~ 0.7 or chi and D to their half values, higher nesep operation was required. In addition, recent investigations of physics models (temperature-gradient force on impurity, photon transport, neutral–neutral collision) under the DEMO relevant SOL and divertor condition are presented.
書誌情報 PROCESSES; Special Issue Computational Fluid Dynamics (CFD) Simulations for Fusion Reactors

巻 10, 号 5, p. 872, 発行日 2022-04
出版者
出版者 MDPI
ISSN
収録物識別子タイプ ISSN
収録物識別子 2227-9717
DOI
識別子タイプ DOI
関連識別子 10.3390/pr10050872
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.3390/pr10050872
戻る
0
views
See details
Views

Versions

Ver.1 2023-05-15 16:49:12.464885
Show All versions

Share

Mendeley Twitter Facebook Print Addthis

Cite as

エクスポート

OAI-PMH
  • OAI-PMH JPCOAR 2.0
  • OAI-PMH JPCOAR 1.0
  • OAI-PMH DublinCore
  • OAI-PMH DDI
Other Formats
  • JSON
  • BIBTEX

Confirm


Powered by WEKO3


Powered by WEKO3