Development of Neutronic Model of Hybrid DEMO-FNS Reactor by Means of NESTOR Code and Monte Carlo Method

被引:0
|
作者
Shlenskii, M. N. [1 ,2 ]
Dlougach, E. D. [1 ]
Kuteev, B. V. [1 ]
机构
[1] Natl Res Ctr, Kurchatov Inst, Moscow 123098, Russia
[2] Natl Res Nucl Univ MEPhI, Moscow 115409, Russia
关键词
fusion neutron source (FNS); neutral beam injection (NBI); plasma modeling; neutron yield; neutron wall loading (NWL); neutron models; Monte Carlo method; TOKAMAK; PLASMA; YIELD;
D O I
10.1134/S1063778823140120
中图分类号
O57 [原子核物理学、高能物理学];
学科分类号
070202 ;
摘要
The paper is devoted to the creation of an improved neutron plasma model of the hybrid reactor facility (HRF) DEMO-FNS, which has been used by codes implementing the Monte Carlo method for modeling radiation transport (MCNP and SuperMC). The old simplified model of the neutron source did not take into account the effect of the neutral injection on the intensity distribution of the fusion reaction rate, and it also had an unrealistic shape (ellipsoidal in vertical section). A new model has been developed on the basis of current data of temperature and density distributions in plasma. The model is built on the basis of current ideas about temperature and density distributions in plasma, takes into account the high contribution of neutral injection to the formation of a population of fast ions, and is also specified by an array of elementary volumes. This makes it possible to set an arbitrary shape of the neutron generation intensity distribution with the required accuracy. The influence of the plasma shape on the distribution of the primary (not scattered) neutron flux along the poloidal angle, as well as on neutron transfer and related processes outside the plasma (in the blanket, and first wall), is shown.
引用
收藏
页码:S134 / S146
页数:13
相关论文
共 50 条
  • [21] Contributions of each isotope in some fluids on neutronic performance in a fusion-fission hybrid reactor: a Monte Carlo method
    Gunay, M.
    Sarer, B.
    Kasap, H.
    INDIAN JOURNAL OF PHYSICS, 2014, 88 (08) : 861 - 866
  • [22] Hybrid evaporator model: Analysis under uncertainty by means of Monte Carlo method
    Colorado, Dario
    Ding, Xudong
    Alfredo Hernandez, J.
    Alonso, Beatriz
    APPLIED THERMAL ENGINEERING, 2012, 43 : 148 - 152
  • [23] Development of repeat geometry function in reactor Monte Carlo code RMC
    Sun, Jialong
    Yu, Ganglin
    She, Ding
    Wang, Kan
    Qiangjiguang Yu Lizishu/High Power Laser and Particle Beams, 2013, 25 (01): : 219 - 222
  • [24] Development of burnup calculation function in reactor Monte Carlo code RMC
    She, D., 2012, Yuan Zi Neng Chuban She (33):
  • [25] RMC1.0-DEVELOPMENT OF MONTE CARLO CODE FOR REACTOR ANALYSIS
    She Ding
    Xu Qi
    Wang Kan
    Yu Ganglin
    PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING 2010, VOL 2, 2011, : 127 - 131
  • [26] TRIPOLI-4® Monte Carlo code ITER A-lite neutronic model validation
    Jaboulay, Jean-Charles
    Cayla, Pierre-Yves
    Fausser, Clement
    Damian, Frederic
    Lee, Yi-Kang
    Puma, Antonella Li
    Trama, Jean-Christophe
    FUSION ENGINEERING AND DESIGN, 2014, 89 (9-10) : 2174 - 2178
  • [27] The effect of different fuels and clads on neutronic calculations in a boiling water reactor using the Monte Carlo method
    Mehtap Düz
    Selcan İnal
    Scientific Reports, 10
  • [28] The effect of different fuels and clads on neutronic calculations in a boiling water reactor using the Monte Carlo method
    Duz, Mehtap
    Inal, Selcan
    SCIENTIFIC REPORTS, 2020, 10 (01)
  • [29] Development of Reactor Physics Monte Carlo Model for MIT BEAVRS
    Sulaiman, Muhammad
    Chaudri, Khurrum Saleem
    Ahmad, Masroor
    2015 POWER GENERATION SYSTEMS AND RENEWABLE ENERGY TECHNOLOGIES (PGSRET-2015), 2015, : 15 - 17
  • [30] Neutronic simulation of Traveling Wave Reactor (TWR) core in multi-cycles using Monte Carlo method
    Dorcheh, Lida Amanelahi
    Saadi, Mohsen Kheradmand
    KERNTECHNIK, 2024, 89 (03) : 283 - 291