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

Nuclear analysis of structural damage and nuclear heating on enhanced K-DEMO divertor model

J. Park, K. Im, S. Kwon, J. Kim, D. Kim, M. Woo, C. Shin2017年被引用 6Nuclear FusionIF 3出版社

This paper addresses nuclear analysis on the Korean fusion demonstration reactor (K-DEMO) divertor to estimate the overall trend of nuclear heating values and displacement damages. The K-DEMO divertor model was created and converted by the CAD (Pro-Engineer™) and Monte Carlo automatic modeling programs as a 22.5° sector of the tokamak. The Monte Carlo neutron photon transport and ADVANTG codes were used in this calculation with the FENDL-2.1 nuclear data library. The calculation results indicate that the highest values appeared on the upper outboard target (OT) area, which means the OT is exposed to the highest radiation conditions among the three plasma-facing parts (inboard, central and outboard) in the divertor. Especially, much lower nuclear heating values and displacement damages are indicated on the lower part of the OT area than others. These are important results contributing to thermal-hydraulic and thermo-mechanical analyses on the divertor and also it is expected that the copper alloy materials may be partially used as a heat sink only at the lower part of the OT instead of the reduced activation ferritic-martensitic steel due to copper alloy's high thermal conductivity.

日本語訳

本論文は、韓国核融合実証炉(K-DEMO)ダイバータにおける核解析を取り扱い、核発熱量と変位損傷の全体的な傾向を評価するものである。K-DEMOダイバータモデルは、CAD(Pro-Engineer™)およびモンテカルロ自動モデリングプログラムを用いて、トカマクの22.5°セクターとして作成・変換された。計算には、モンテカルロ中性子・光子輸送コードおよびADVANTGコードを、FENDL-2.1核データライブラリとともに使用した。計算結果によれば、上部アウターダイバータ(OT)領域で最も高い値が示され、これはダイバータの3つのプラズマ対向部(インボード、センター、アウトボード)の中でOTが最も高い放射線条件に曝されていることを意味する。特に、OT領域の下部では、他の領域と比較して核発熱量と変位損傷が大幅に低い値となることが示された。これらの結果は、ダイバータの熱流動解析および熱機械解析に寄与する重要なものであり、また、銅合金の高い熱伝導率により、OT下部のみにおいて、低放射化フェライト・マルテンサイト鋼の代わりに銅合金を熱シンクとして部分的に使用できる可能性が期待される。

wiki

DivertorDEMODEMO divertorK-DEMO
この論文にはまだAI要約がありません。

関連論文

Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO

2017Nuclear Fusion

Engineering design of the TITAN-II divertor

1989Fusion Engineering and Design

Strain mapping and defects inspection of divertor targets by Bragg edge neutron imaging and neutron tomography

2025Nuclear Fusion

Stability analysis of divertor plasma transport using the CSD model

2026Plasma Physics and Controlled Fusion

Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors

2018Nuclear Fusion

Impurity seeding for tokamak power exhaust: from present devices via ITER to DEMO

2013Plasma Physics and Controlled Fusion

Liquid-metal-cooled divertor for ARIES

1995Fusion Engineering and Design

A novel liquid lithium jet-cooled finger-type divertor target concept for fusion power plant application

2021Nuclear Fusion

Three dimensional analysis of design-modification effects on neutron streaming through the net divertor duct

1989Fusion Engineering and Design

Self-consistent modelling of a liquid metal box-type divertor with application to the divertor tokamak test facility: Li versus Sn

2019Nuclear Fusion