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

被引:7
|
作者
Park, J. [1 ]
Im, K. [1 ]
Kwon, S. [1 ]
Kim, J. [2 ]
Kim, D. [2 ]
Woo, M. [2 ]
Shin, C. [2 ]
机构
[1] Natl Fus Res Inst, Daejeon, South Korea
[2] Hanyang Univ, Nucl Engn Dept, Seoul, South Korea
关键词
K-DEMO; divertor; neutronic analysis; radiation damage; dpa; MCNP; FUSION POWER-PLANT; NEUTRONIC ANALYSIS; MCNP;
D O I
10.1088/1741-4326/aa835a
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
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 (TM)) and Monte Carlo automatic modeling programs as a 22.5 degrees 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.
引用
收藏
页数:5
相关论文
共 50 条
  • [1] Development of the K-DEMO Divertor Concept
    Im, K.
    Park, J. S.
    Kwon, S.
    2015 IEEE 26TH SYMPOSIUM ON FUSION ENGINEERING (SOFE), 2015,
  • [2] A Preliminary Development of the K-DEMO Divertor Concept
    Im, Kihak
    Kwon, Sungjin
    Park, Jong Sung
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2016, 44 (10) : 2493 - 2501
  • [3] Recent progress in the design of the K-DEMO divertor
    Kwon, Sungjin
    Im, Kihak
    Hong, Suk-Ho
    Lee, Hyungho
    Rognlien, Thomas D.
    Meyer, William
    Kim, Keeman
    FUSION ENGINEERING AND DESIGN, 2020, 159
  • [4] Preliminary electromagnetic loads calculation for the divertor of K-DEMO
    Kwon, Sungjin
    Im, Kihak
    Lee, Youngmin
    Hong, Suk-Ho
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 2135 - 2139
  • [5] Nuclear heating and helium production at the inboard divertor rail for DEMO
    Tracz, Grzegorz
    FUSION ENGINEERING AND DESIGN, 2014, 89 (12) : 2981 - 2987
  • [6] Survey of heating and current drive for K-DEMO
    Mikkelsen, D. R.
    Kessel, C. E.
    Poli, F. M.
    Bertelli, N.
    Kim, K.
    NUCLEAR FUSION, 2018, 58 (03)
  • [7] Thermohydraulic Assessment for the Modified Concept of the K-DEMO Divertor Target
    Kwon, Sungjin
    Im, Kihak
    Park, Jong Sung
    FUSION SCIENCE AND TECHNOLOGY, 2017, 72 (04) : 737 - 746
  • [8] Nuclear heating and damage profiles in the ITER divertor cassette
    Sawan, ME
    Santoro, RT
    17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2, 1998, : 833 - 836
  • [9] Nuclear fusion waste classification of K-DEMO under the Korean radioactive waste regulations
    Kim, Byung Chul
    NUCLEAR FUSION, 2023, 63 (01)
  • [10] Analysis of the nuclear loads on Chromium monoblock divertor target for DEMO
    Noce, Simone
    Flammini, Davide
    Gaudio, Pasquale
    Gelfusa, Michela
    Mazzone, Giuseppe
    Moro, Fabio
    Romanelli, Francesco
    Villari, Rosaria
    Wyss, Ivan
    You, Jeong-Ha
    FUSION ENGINEERING AND DESIGN, 2023, 194