Mathematical Model of the Technological Process of Carbothermal Synthesis of Mixed Uranium-Plutonium Nitride Fuel

被引:0
|
作者
Blank, M. O. [1 ]
Egorova, O. V. [1 ]
Liventsova, N. V. [1 ]
Liventsov, S. N. [1 ]
Schmidt, O. V. [2 ]
机构
[1] Tomsk Polytech Univ TPU, Tomsk, Russia
[2] Bochvar High Technol Res Inst Inorgan Mat VNIINM, Moscow, Russia
关键词
MONONITRIDE; MECHANISM; KINETICS;
D O I
10.1007/s10512-021-00757-0
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
A mathematical model of the technological process of the carbothermal synthesis of mixed uranium-plutonium nitride fuel is presented. The model was developed for use in the KOD TP software complex - a code for optimization and diagnostics of technological processes. The applied studies performed in this work are aimed at determining the optimal technological modes and increasing the efficiency of the development and tuning of process control systems as well as expanding the functionality of the KOD TP. The main characteristics of the process are described and the requirements of the model and assumptions are formulated. Computational experiments were performed. It was shown that the model is efficient and that it can be used to develop control systems, optimize regimes, and simulate equipment failures in the course of industrial operation.
引用
收藏
页码:331 / 336
页数:6
相关论文
共 50 条
  • [41] Pyrochemical conversion of weapons plutonium into plutonium mononitride, monocarbide and mixed uranium-plutonium fuel for fast reactors
    B. D. Rogozkin
    F. G. Reshetnikov
    N. M. Stepennova
    Yu. E. Fedorov
    M. G. Shishkov
    E. M. Glagovskii
    V. Yu. Rogozhkin
    Atomic Energy, 2011, 109 : 189 - 196
  • [42] PROGRAM AND SOME RESULTS OF PRE-REACTOR STUDIES OF MIXED URANIUM-PLUTONIUM NITRIDE FUEL FOR FAST REACTORS
    Troyanov, V. M.
    Grachev, A. F.
    Zabud'ko, L. M.
    Skupov, M. V.
    Kireev, G. A.
    ATOMIC ENERGY, 2015, 117 (04) : 236 - 242
  • [43] Program and Some Results of Pre-Reactor Studies of Mixed Uranium-Plutonium Nitride Fuel for Fast Reactors
    V. M. Troyanov
    A. F. Grachev
    L. M. Zabud’ko
    M. V. Skupov
    G. A. Kireev
    Atomic Energy, 2015, 117 : 236 - 242
  • [44] PYROCHEMICAL CONVERSION OF WEAPONS PLUTONIUM INTO PLUTONIUM MONONITRIDE, MONOCARBIDE AND MIXED URANIUM-PLUTONIUM FUEL FOR FAST REACTORS
    Rogozkin, B. D.
    Reshetnikov, F. G.
    Stepennova, N. M.
    Fedorov, Yu. E.
    Shishkov, M. G.
    Glagovskii, E. M.
    Rogozhkin, V. Yu.
    ATOMIC ENERGY, 2011, 109 (03) : 189 - 196
  • [45] Determining the Specific Activity of Carbon-14 in Samples of Irradiated Mixed Nitride Uranium-Plutonium Nuclear Fuel
    V. N. Momotov
    E. A. Erin
    A. Yu. Volkov
    D. E. Tikhonova
    A. S. Kupriyanov
    A. Yu. Shadrin
    Radiochemistry, 2021, 63 : 364 - 368
  • [46] Determining the Specific Activity of Carbon-14 in Samples of Irradiated Mixed Nitride Uranium-Plutonium Nuclear Fuel
    Momotov, V. N.
    Erin, E. A.
    Volkov, A. Yu
    Tikhonova, D. E.
    Kupriyanov, A. S.
    Shadrin, A. Yu
    RADIOCHEMISTRY, 2021, 63 (03) : 364 - 368
  • [47] URANIUM-PLUTONIUM REDISTRIBUTION IN MIXED-OXIDE FUELS - MODEL PREDICTIONS AND FUEL PIN DATA
    MELDE, GF
    AMERICAN CERAMIC SOCIETY BULLETIN, 1972, 51 (04): : 387 - &
  • [48] COMPUTATIONAL MODEL FOR THE OXYGEN POTENTIALS OF MIXED URANIUM-PLUTONIUM OXIDE
    KRISHNAIAH, MV
    SRIRAMAMURTI, P
    JOURNAL OF THE AMERICAN CERAMIC SOCIETY, 1984, 67 (08) : 568 - 571
  • [49] Use of mixed uranium-plutonium fuel with different burnable absorbers in RBMK reactors
    A. A. Balygin
    E. V. Burlakov
    A. V. Krayushkin
    V. G. Novikov
    Yu. A. Tishkin
    A. M. Fedosov
    Atomic Energy, 1999, 86 : 161 - 164
  • [50] Thermogravimetric study of mixed uranium-plutonium fuel for prospective generation IV reactors
    Krivov, M. P.
    Kireev, G. A.
    Tenishev, A. V.
    Davydov, A. V.
    Skupov, M. V.
    Solomatin, I. D.
    Mosunova, N. A.
    Usov, E. V.
    Chukhno, V. I.
    JOURNAL OF NUCLEAR MATERIALS, 2022, 567