METHOD FOR SIMULATING TRANSIENT PROCESS IN NUCLEAR REACTOR Russian patent published in 1995 - IPC

Abstract RU 2044347 C1

FIELD: primarily, in experimental test facilities and simulators for personnel of nuclear power plants. SUBSTANCE: method involves use of experimental section simulating thermal and hydraulic processes in reactor core. Section has at least one heater provided, as a rule, with several units incorporating provision for independent control of energy release both lengthwise and over its perimeter. Heater simulates structural member of reactor core. Energy release in heater units is controlled by means of computer operating in real-time mode and using data on temperature of coolant flowing over heater surface. Volume steam content and/or coolant density is measured in one or more sectional areas of experimental section. Data on steam content and/or coolant density obtained during measurements and results of calculation of core structural member temperatures are used in neutron-physics calculations of nuclear reactor kinetics. Output data of such calculations are capacities of internal heat sources used in solving heat conduction equations for simulated structural member of reactor core. Computer functions to compensate for difference in calculated values of heat fluxes on heater surfaces over which coolant flows and over surfaces of core structural member simulated by this heater. EFFECT: improved precision of process simulation. 5 cl

Similar patents RU2044347C1

Title Year Author Number
FUEL ASSEMBLY, CORE, AND OPERATING PROCESS OF WATER-COOLED NUCLEAR REACTOR 2001
  • Stoljarevskij A.Ja.
RU2214633C2
METHOD FOR DETERMINING HEAT FLOW AND TEMPERATURE FIELDS IN NUCLEAR REACTOR FUEL ASSEMBLY 1997
  • Gol'Ba V.S.
  • Ivanenko I.Ju.
RU2129313C1
METHOD FOR EVALUATING BURNOUT MARGIN IN NUCLEAR POWER UNITS 2003
  • Boltenko Eh.A.
RU2256962C2
METHOD FOR EVALUATING STEAM VOID COEFFICIENT OF REACTIVITY 2006
  • Moiseev Igor' Fedorovich
  • Fadeev Aleksandr Nikolaevich
RU2315377C1
WATER-COOLED NUCLEAR REACTOR 1992
  • Bogojavlenskij R.G.
  • Gol'Tsev A.O.
  • Doronin A.S.
  • Mosevitskij I.S.
  • Popov S.V.
  • Udjanskij Ju.N.
  • Tsibul'Skij V.F.
RU2032946C1
NUCLEAR REACTOR FUEL ELEMENT SIMULATOR 2013
  • Daragan Viktor Danilovich
  • Mel'Nikov Gennadij Nikolaevich
  • Soldatkin Dmitrij Mikhajlovich
RU2523423C1
METHOD OF DETERMINING STEAM COEFFICIENT OF REACTIVITY 2011
  • Fadeev Aleksandr Nikolaevich
  • Moiseev Igor' Fedorovich
RU2465660C1
WATER-MODERATED POWER REACTOR CORE 1997
  • Alekseev P.N.
  • Gorokhov V.F.
  • Doronin A.S.
  • Dukhovenskij A.S.
  • Zhurbenko A.V.
  • Lunin G.L.
  • Proshkin A.A.
  • Panjushkin A.K.
  • Mezhuev V.A.
  • Potoskaev G.G.
  • Kurskov V.S.
  • Bek E.G.
  • Ivanov A.V.
  • Fedorov V.G.
  • Vasil'Chenko I.N.
  • Demin E.D.
RU2126999C1
METHOD FOR ON-LINE INSPECTION OF FUEL CONDITION IN NUCLEAR REACTOR FUEL ASSEMBLY 1992
  • Sokolov Aleksandr Petrovich
RU2068205C1
FUEL ASSEMBLY (VERSIONS) AND OPERATION METHOD THEREOF 2014
  • Grishanin Evgenij Ivanovich
  • Alekseev Pavel Nikolaevich
  • Fonarev Boris Il'Ich
RU2558656C1

RU 2 044 347 C1

Authors

Gridnev E.A.

Savvatimskij G.I.

Dates

1995-09-20Published

1991-10-09Filed