AN ANALYSIS OF POWER EXCURSION IN TRIGA-II
Journal Article
·
· J. Korean Soc. Mech. Engrs.
OSTI ID:4785294
An approximate method for analyzing a power excursion in a nuclear reactor, is proposed. The analysis is based on an equivalent model core of a reactor simplified by hotspot-factors and consists of a nonlinear sinrultaneous differential equation. The original purpose is to evaluate a possible incident of maximum power excursion in TRIGA-II. In this case, the primary nuclear shutdown mechanism is solely by negative temperature coefficient, since the fuel surface temperature is below the saturation temperature of the coolant water, under the condition of the maximum of the inserted excess reactivity. Hence, the effect of the steam void generated in the water moderator or the radiolytic gas formation is ignored. Furthermore, the effect of delayed neutrons is also ignored, since the inserted excess reactivity of 2 dollars is much more than 1 dollar and enritters of delayed neutrons have much longer decay halflives than the duraiion of power burst. The results agree with experiments which have been carried out in GA, so far as the inserted excess reactivities are more than 2 dollars and no formation of steam voids occurs. A phase-plane analysis of the equations representing nuclear power excursion is presented and the characteristics of inherent safety for the nuclear excursion in TRIGA-II are shown. (auth)
- Research Organization:
- Seoul National Univ., Korea
- NSA Number:
- NSA-16-034118
- OSTI ID:
- 4785294
- Journal Information:
- J. Korean Soc. Mech. Engrs., Journal Name: J. Korean Soc. Mech. Engrs. Vol. Vol: 2
- Country of Publication:
- Country unknown/Code not available
- Language:
- English
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Related Subjects
BURNOUT
DECOMPOSITION
DELAYED NEUTRONS
DIFFERENTIAL EQUATIONS
EQUATIONS
EXCURSIONS
FLUID FLOW
FUEL ELEMENTS
GASES
MATHEMATICS
POWER
PULSES
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RESEARCH REACTORS
SHUTDOWN
STEAM
SURFACES
TEMPERATURE
TRANSFER FUNCTIONS
VARIATIONS
WATER COOLANT
ZONES
DECOMPOSITION
DELAYED NEUTRONS
DIFFERENTIAL EQUATIONS
EQUATIONS
EXCURSIONS
FLUID FLOW
FUEL ELEMENTS
GASES
MATHEMATICS
POWER
PULSES
REACTIVITY
REACTOR CORE
REACTOR SAFETY
REACTOR TECHNOLOGY
RESEARCH REACTORS
SHUTDOWN
STEAM
SURFACES
TEMPERATURE
TRANSFER FUNCTIONS
VARIATIONS
WATER COOLANT
ZONES