COOLANT MIXING IN THE VVER-440 FUEL ASSEMBLY HEAD

被引:0
|
作者
Romsy, Tomas [1 ]
Zacha, Pavel [1 ]
机构
[1] CTU, Fac Mech Engn, Prague, Czech Republic
关键词
D O I
暂无
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
The issue of the temperature measurement in a nuclear reactor is an important element to ensure safe operation of the nuclear power plant. To prevent damages and radioactive releases the fuel in the reactor must be continuously cooled. The coolant temperature field of the VVER-440 reactor. is measured with thermocouples installed at the outlet part of fuel assemblies. Since the power output of the fuel pins is not equal, a non-uniform temperature field at the inlet of the fuel assembly head is formed. Next, the temperature field is subsequently mixed by passing through the assembly head, which contains some constructional elements helping to mixing coolant flow. This mixing is not perfect and due to the effect described above, the signal on the thermocouple can be affected. This phenomenon was introduced in 2009 Atomic Energy Research (AER) Symposium in Bulgaria. 7 international institutions participated with the main goal to explain the mixing character of the coolant and to compare results. For further study of this phenomenon the new detailed computational model of the upper part of the fuel assembly was created and subsequently on the ANSYS FLUENT CFD code verified. The main output of these simulations is study of the coolant temperature distribution on the thermocouple. Computational model, based on the source geometry given by AER symposium, was created in preprocessor GAMBIT 2.4.6. Model contains over 13 million hexahedral cells. Thermohydraulic simulations where performed in ANSYS FLUENT v14.5 and results were compared with data from AER Symposium. There were considered two cases with different pins power outputs. With compare to AER symposium results the achieved resultant temperature on the thermocouple position for both cases indicate comparable accuracy. Furthermore, some flow fluctuations in the assembly head area where found.
引用
收藏
页数:7
相关论文
共 50 条
  • [41] THE RESULTS OF POSTIRRADIATION EXAMINATIONS OF VVER-1000 AND VVER-440 FUEL-RODS
    DUBROVIN, KP
    IVANOV, EG
    STRIJOV, PN
    YAKOVLEV, VV
    JOURNAL OF NUCLEAR MATERIALS, 1991, 178 (2-3) : 306 - 311
  • [42] EFFECTIVE FISSION-PRODUCT YIELDS IN VVER-365 AND VVER-440 FUEL
    GABESKIRIYA, VY
    BORISENKOV, VI
    SOVIET ATOMIC ENERGY, 1984, 57 (03): : 660 - 661
  • [43] EVALUATION OF THE CHANGE IN THE CONCENTRATION OF BORIC-ACID ACCOMPANYING THE REPLACEMENT OF ONE FUEL ASSEMBLY IN VVER-440
    AIRAPETYAN, AA
    SOVIET ATOMIC ENERGY, 1988, 64 (06): : 516 - 517
  • [44] SYSTEMATIC-ERRORS IN MEASURING THE COOLANT TEMPERATURE IN A VVER-440 (RADIATION HEATING OF THE THERMOCOUPLES)
    TIMONIN, AS
    MEASUREMENT TECHNIQUES USSR, 1993, 36 (05): : 577 - 580
  • [45] DETERMINING THE TRITIUM CONTENT IN THE CLAD OF VVER-440 FUEL-RODS
    BABENKO, AG
    MEKHEDOV, BN
    POPOV, SV
    SHALIN, AN
    SOVIET ATOMIC ENERGY, 1991, 71 (03): : 773 - 775
  • [46] Verification of Power Distribution of Real Fuel Loadings in VVER-440 Reactor
    Vrban, Branislav
    Cerba, Stefan
    Farkas, Gabriel
    Hascik, Jan
    Luley, Jakub
    Necas, Vladimir
    Urban, Peter
    23RD INTERNATIONAL CONFERENCE NUCLEAR ENERGY FOR NEW EUROPE, (NENE 2014), 2014,
  • [47] DETERMINATION OF FUEL BURNUP IN VVER-440 ASSEMBLIES WITH AN ARAGONIT RADIATION METER
    MILLER, OA
    GOLUBEV, LI
    KULAKOV, GA
    EFREMOV, YV
    SOVIET ATOMIC ENERGY, 1979, 46 (05): : 410 - 411
  • [48] SYSTEMATIC-ERRORS IN MEASURING THE COOLANT TEMPERATURE IN VVER-440 REACTORS (DYNAMIC ERRORS)
    TIMONIN, AS
    MEASUREMENT TECHNIQUES USSR, 1993, 36 (04): : 427 - 431
  • [49] ACCUMULATION OF U-232 IN THE CYCLIC UTILIZATION OF FUEL IN THE VVER-440
    ZARITSKAYA, TS
    MATVEEV, LV
    RUDIK, AP
    TSENTER, EM
    SOVIET ATOMIC ENERGY, 1983, 54 (05): : 332 - 335
  • [50] Increase of VVER-440 fuel cycle length up to 18 months
    Proselkov, V.N.
    Pechikin, V.A.
    Simonov, K.V.
    Panin, M.V.
    Pytkin, Yu.N.
    Atomnaya Energiya, 1991, 71 (05): : 466 - 470