Computational Challenges of Fusion Neutronics for ITER Ports

被引:3
|
作者
Serikov, A. [1 ]
Fischer, U. [1 ]
Pitcher, C. S. [2 ]
Suarez, A. [2 ]
Weinhorst, B. [1 ]
机构
[1] Karlsruhe Inst Technol, Inst Neutron Phys & Reactor Technol, Hermann von Helmholtz Pl 1, D-76344 Eggenstein Leopoldshafen, Germany
[2] ITER Org, Route Vinon Sur Verdon, F-13115 St Paul Les Durance, France
关键词
ITER; diagnostics ports; fusion neutronics; MCNP; R2Smesh and D1S methods; Shut-Down Dose Rate (SDDR); Helios supercomputer; CASCADES;
D O I
10.1051/sname/201401502
中图分类号
TP39 [计算机的应用];
学科分类号
081203 ; 0835 ;
摘要
This paper elaborates computational challenges tackled for providing neutronics service supplied for developing the design of the Diagnostics Equatorial and Upper Port Plugs (EPP and UPP). The aim was to guide and assist the EPP and UPP design developers with optimal shielding solutions which are characterised of maintain the diagnostics purposes of the systems together with adequate radiation shielding performance. The target parameter for the shielding optimization was the minimum of Shut-Down Dose Rate (SDDR) inside the interspace between the port back-side and ITER bioshield. This aim was reached by parametric neutronic analyses of the shielding geometry and material composition, mitigating direct streaming of neutrons from the plasma by arranging the labyrinths and horizontal rails. Variation of many geometrical parameters of the labyrinths was possible only by applying the high performance parallel computations with MCNP5 using pure MPI and hybrid OpenMP/MPI parallelization techniques on several available supercomputers. MCNP5 parallel performance assessments were carried out to find an efficient way to run the code in a parallel regime. It was found a strong scaling (up to 4096 cores) performance of the MCNP5 jobs running with analogue Monte Carlo sampling and weak scaling for the tasks with biased sampling as a variance reduction technique, such as the MCNP5 intrinsic weight window generator. Deep penetrating radiation in the complex ITER tokamak geometry combined blocks of strong attenuation of the radiation together with the void gaps along which the particles are streamed freely contributes to computation challenges of radiation transport.
引用
下载
收藏
页数:12
相关论文
共 50 条
  • [1] Neutronics for equatorial and upper ports in ITER
    Serikov, A.
    Fischer, U.
    Henderson, M.
    Leichtle, D.
    Pitcher, C. S.
    Spaeh, P.
    Strauss, D.
    Suarez, A.
    Weinhorst, B.
    FUSION ENGINEERING AND DESIGN, 2013, 88 (9-10) : 1965 - 1968
  • [2] Neutronics for ITER diagnostic systems and ports
    Shatalov, G
    Borisov, A
    Sheludjakov, S
    Serikov, A
    FUSION ENGINEERING AND DESIGN, 1998, 42 : 221 - 228
  • [3] Neutronics Design of Fusion Reactor-Based Boron Neutron Capture Therapy in ITER
    Murata, Isao
    Tamaki, Shingo
    Kusaka, Sachie
    Maemunah, Indah Rosidah
    Sato, Fuminobu
    Miyamaru, Hiroyuki
    Yoshida, Shigeo
    FUSION SCIENCE AND TECHNOLOGY, 2023, 79 (04) : 465 - 475
  • [4] On the strategy and requirements for neutronics testing in ITER
    Youssef, MZ
    Sawan, ME
    FUSION SCIENCE AND TECHNOLOGY, 2005, 47 (04) : 1038 - 1045
  • [5] Progress in neutronics for the ITER ECRH launcher
    Serikov, Arkady
    Fischer, Ulrich
    Heidinger, Roland
    Kleefeldt, Klaus
    Spaeh, Peter
    Stickel, Stephanie
    Tsige-Tamirat, Haileyesus
    FUSION ENGINEERING AND DESIGN, 2008, 83 (10-12) : 1631 - 1637
  • [6] Neutronics experiment to simulate ITER shield
    Chen, Yuan
    Liu, Rong
    Shen, Jian
    Guo, Haipin
    Liu, Yuan
    Jiang, Wenmian
    Fusion Technology, 1998, 34 (3 pt 2): : 1023 - 1027
  • [7] Neutronics analysis for ITER cable looms
    Serikov, Arkady
    Bertalot, Luciano
    Clough, Matthew
    Fischer, Ulrich
    Suarez, Alejandro
    FUSION ENGINEERING AND DESIGN, 2015, 96-97 : 943 - 947
  • [8] Neutronics experiment to stimulate ITER shield
    Chen, Y
    Liu, R
    Shen, J
    Guo, HP
    Liu, Y
    Jiang, WM
    FUSION TECHNOLOGY, 1998, 34 (03): : 1023 - 1027
  • [9] ITER radiation shielding and neutronics analysis
    Santoro, RT
    Iida, H
    Khripunov, V
    Sawan, M
    Inoue, T
    FUSION ENGINEERING AND DESIGN, 1998, 39-40 : 593 - 599
  • [10] Neutronics experiments for ITER at JAERI/FNS
    Konno, C
    Maekawa, F
    Kasugai, Y
    Uno, Y
    Kaneko, J
    Nishitani, T
    Wada, M
    Ikeda, Y
    Takeuchi, H
    NUCLEAR FUSION, 2001, 41 (03) : 333 - 337