FIELD: monitoring safety characteristics and variables of nuclear power units at nuclear power stations.
SUBSTANCE: proposed method that can be used, for instance, to adjust reactimeters of nuclear power stations with type RBMK-1000 and incorporates provision for reducing systematic measurement error by two orders of magnitude includes introduction of sets of variables characterizing correlation between fissionable elements of fuel and desired burn-up step in charge-coupled device module of reactimeter; determination of current value of mean fuel burn-up using data of centralized checkup system of reactor unit; and selection of respective mentioned variables by varying position of switch on rear panel of reactimeter. Use is made of sets of variables αi (fractions of i group delayed neutrons in delayed neutron generation responsible for total composition of fissionable isotopes of desired burn-up fuel) and sets of variables λeff (effective constants of i group delayed neutrons). Reactimeter adjustment scale is calibrated in terms of mean fuel burn-up in reactor core.
EFFECT: enhanced measurement accuracy, and nuclear safety, facilitated adjustment to current state of reactor by composition of fissionable elements of fuel.
2 cl 3 tbl
Title | Year | Author | Number |
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METHOD FOR ADJUSTING DIGITAL REACTIVITY METERS TO CURRENT CONDITION OF REACTOR BY COMPOSITION OF FUEL FISSIONABLE ELEMENTS | 2002 |
|
RU2239894C2 |
METHOD FOR ENERGY GENERATION FROM NUCLEAR FUEL, POWER AMPLIFIER IMPLEMENTING THIS METHOD, AND ENERGY GENERATING PLANT | 1994 |
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RU2178209C2 |
METHOD FOR NUCLEAR FUEL CYCLING IN GRAPHITE-MODERATED PRESSURIZED-TUBE REACTOR | 2002 |
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PROCESS CHANNEL COMBINED FOR INDUSTRIAL NUCLEAR PLANT | 2015 |
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RU2577783C1 |
STANDING WAVE NUCLEAR FISSION REACTOR AND METHODS | 2010 |
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RU2552648C2 |
METHOD FOR ON-LINE INSPECTION OF FUEL CONDITION IN NUCLEAR REACTOR FUEL ASSEMBLY | 1992 |
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RU2068205C1 |
FUEL CYCLE CONTROL METHOD FOR PRESSURE-TUBE REACTOR | 2001 |
|
RU2218612C2 |
METHOD OF ENSURING SUBCRITICALITY OF FAST REACTOR CORE WITH UNCERTAINTY OF NEUTRON-PHYSICAL CHARACTERISTICS THEREOF | 2013 |
|
RU2546662C1 |
HEAT-DIVIDING ELEMENT OF A NUCLEAR ENERGY REACTOR ON FAST NEUTRONS | 2018 |
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RU2680252C1 |
COMBINED PELLET OF NUCLEAR FUEL | 2010 |
|
RU2427936C1 |
Authors
Dates
2005-01-10—Published
2003-04-30—Filed