Mathematical modeling of steamgeneator PGV-1000, used in nuclear power plant with WWER-1000 nuclear reactor

被引：0
|
作者：
Monev, Vladimir M. [1 ]
Filipov, Kalin B. [2 ]
机构：
[1] Kozloduy Nucl Power Plant, Kozloduy, Bulgaria
[2] Tech Univ Sofia, Dept Thermal & Nucl Power Engn, Sofia, Bulgaria
来源：
PROCEEDINGS OF THE 2021 6TH INTERNATIONAL SYMPOSIUM ON ENVIRONMENT - FRIENDLY ENERGIES AND APPLICATIONS (EFEA 2021) | 2021年
关键词：
Nuclear power plant; steam generator; heat transfer; simulation modelling; nuclear safety; MATLAB;
D O I：
10.1109/EFEA49713.2021.9406229
中图分类号：
X [环境科学、安全科学];
学科分类号：
08 ; 0830 ;
摘要：
Proper operation of steam generators in nuclear power plants is critical for the nuclear safety. In this research is developed simplified mathematical model of steam generator PGV-1000, used in eastern-type pressurized water reactors WWER-1000. The mathematical model uses an interpolation between the primary quantities in the primary loop, which can be used to solve the heat transfer problem under non-nominal operational conditions. The accumulation of deposits over the tube bundle and the tube failure in the tube bundle are analyzed.
引用
收藏
页数：6
相关论文
共 50 条
  • [21] Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
    Papi, Zahra
    Khoshahval, Farrokh
    Pour-Imani, Reza
    KERNTECHNIK, 2023, 88 (01) : 33 - 42
  • [22] Features of Temperature Control of Fuel Element Cladding for Pressurized Water Nuclear Reactor "WWER-1000" While Simulating Reactor Accidents
    Zaytsev, P. A.
    Priymak, S. V.
    Usachev, V. B.
    Oleynikov, P. P.
    Soldatkin, D. M.
    TEMPERATURE: ITS MEASUREMENT AND CONTROL IN SCIENCE AND INDUSTRY, VOL 8, 2013, 1552 : 845 - 850
  • [23] Radiation balance when developing the nuclear power engineering (NPE) with the BREST-1200 and WWER-1000 reactors
    Ganeev, I.Kh.
    Lopatkin, A.V.
    Orlov, V.V.
    Atomnaya Energiya, 2001, 91 (05): : 337 - 343
  • [24] Development of external coupling for calculation of the control rod worth in terms of burn-up for a WWER-1000 nuclear reactor
    Noori-Kalkhoran, Omid
    Yarizadeh-Beneh, Mehdi
    Ahangari, Rohollah
    NUCLEAR ENGINEERING AND DESIGN, 2016, 305 : 612 - 625
  • [25] Investigation of critical safety function "Heat sink" at low power and cold condition for Kozloduy Nuclear Power Plant WWER-1000/V320
    Andreeva, M.
    Pavlova, M. P.
    Groudev, P. P.
    ANNALS OF NUCLEAR ENERGY, 2012, 40 (01) : 221 - 228
  • [26] EFFECT OF OUTPUT HEAT FROM WWER-1000 TYPE NUCLEAR-POWER-PLANTS ON ELECTRICAL AND ENERGETIC EFFICIENCIES OF THE UNIT
    KARAFIAT, J
    KERNENERGIE, 1990, 33 (05): : 210 - 213
  • [27] ANALYSIS OF THE INFLUENCE OF NUCLEAR FUEL BURNUP ON THE 16N FORMATION RATE IN THE PRIMARY COOLANT CIRCUIT OF WWER-1000 REACTOR
    Fylonych, Yu
    Zaporozhan, V
    Balashevskyi, O.
    Merkotan, K.
    NUCLEAR PHYSICS AND ATOMIC ENERGY, 2021, 22 (01): : 48 - 55
  • [28] EFFECT OF OUTPUT HEAT FROM WWER-1000 TYPE NUCLEAR-POWER PLANTS ON EVAPORATION IN COOLING-TOWERS
    KARAFIAT, J
    KERNENERGIE, 1989, 32 (12): : 469 - 470
  • [29] COST SAVING WHEN USING ENHANCED CONDUCTIVITY NUCLEAR FUEL CONTAINING BEO IN WWER-1000 REACTORS
    Zahradka, Tomas
    Skoda, Radek
    PROCEEDINGS OF THE 22ND INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2014, VOL 1, 2014,
  • [30] OPTICAL-MECHANICAL MODULE FOR MEASURING THE RESIDUAL STRESS IN METAL OF THE SURFACE OF REACTOR OF POWER UNIT WWER-1000
    Gozhenko, S. V.
    Ozhigov, L. S.
    PROBLEMS OF ATOMIC SCIENCE AND TECHNOLOGY, 2016, (02): : 66 - 71
12345