FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Prompt and non-prompt contributions to fusion product bombardment of a tokamak first wall

L.M. Hively, G.H. Miley1980年被引用 23Nuclear FusionIF 3出版社

High-energy fusion-product losses from an axisymmetric tokamak plasma to the first wall are studied. Prompt-escape bombardment fluxes (i.e. before slowing-down) are calculated including the non-separable dependence of flux as a function of poloidal angle and local angle of incidence at the first wall. The resulting rate of blistering-injected impurities might then reduce reactor burn times by 50–70%. The sensitivity of the bombardment flux to various device parameters is examined; plasma-wall separation is found to be the most crucial factor. Modest increases (≤20%) in wall radius (plasma radius fixed) of a device such as the ORNL-EPR are found to reduce blistering-injected impurities to a level which should no longer limit the burn time. Non-prompt losses (during slowing-down) are also calculated; the resulting flux at the wall ≲ 0.1 × (prompt flux) × .

日本語訳

軸対称トカマクプラズマから第一壁への高エネルギー核融合生成物の損失について研究する。即時脱出衝撃フラックス(すなわち、減速前)を、ポロイダル角と第一壁での局所入射角の関数としてのフラックスの非分離依存性を含めて計算する。結果として生じるブリスタリング注入不純物の割合は、炉の燃焼時間を50〜70%減少させる可能性がある。様々な装置パラメータに対する衝撃フラックスの感度を調べたところ、プラズマ-壁間距離が最も重要な因子であることがわかった。ORNL-EPRのような装置の壁半径を(プラズマ半径を固定して)わずかに増加させる(≤20%)ことで、ブリスタリング注入不純物が燃焼時間を制限しないレベルまで低減できることがわかった。非即時損失(減速中)も計算した。その結果、壁でのフラックスは≲0.1×(即時フラックス)であった。

wiki

First wallFusion product
この論文にはまだAI要約がありません。

関連論文

Fusion product bombardment of a tokamak first wall

1977Nuclear Fusion

The magnitude of plasma flux to the main-wall in the DIII-D tokamak

2005Plasma Physics and Controlled Fusion

A fast, magnetics-free flux surface estimation and q-profile reconstruction algorithm for feedback control of plasma profiles

2013Plasma Physics and Controlled Fusion

Active particle control experiments and critical particle flux discriminating between the wall pumping and fuelling in the compact plasma wall interaction device CPD spherical tokamak

2009Nuclear Fusion

Alpha transport and blistering in tokamaks

1979Nuclear Fusion

Flux dependence of carbon chemical erosion by deuterium ions

2004Nuclear Fusion

Equilibrium reconstruction in the START tokamak

2001Nuclear Fusion

Chapter 8: Plasma operation and control

1999Nuclear Fusion

Kinetic modeling of the plasma–wall interaction in the DTT divertor region

2024Plasma Physics and Controlled Fusion

An electrostatic barrier scrape-off layer for control of core plasma effluxes in tokamaks

1990Plasma Physics and Controlled Fusion