Determination of the specific heat transfer between fuel and canning from reactivity measurements at the nuclear power plant KCB
The reactivity transient following a control rod step strongly depends on quantities that determine the thermal reactivity feedback. For the special case of a pressurized water reactor, these quantities are the reactivity temperature coefficients and the heat transfer between fuel and coolant. Therefore, it is possible to determine these quantities by fitting appropriate model calculations to measured reactivity transients. This so-called rod step method was extensively applied for the first time in the first cycle of the nuclear power plant KCB at Borssele in the Netherlands. The values of the heat transfer between fuel and coolant and those of the fuel temperature coefficient that are obtained by this method agree well with the theoretically expected behavior with increasing core burnup.
- Research Organization:
- Kraftwerk Union AG, Erlangen, Ger.
- OSTI ID:
- 7362807
- Journal Information:
- Nucl. Technol.; (United States), Journal Name: Nucl. Technol.; (United States) Vol. 29:3; ISSN NUTYB
- Country of Publication:
- United States
- Language:
- English
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210200* -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
BORSSELE REACTOR
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ENERGY TRANSFER
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FUEL ELEMENTS
HEAT TRANSFER
KINETICS
POWER REACTORS
PWR TYPE REACTORS
REACTIVITY COEFFICIENTS
REACTOR COMPONENTS
REACTOR KINETICS
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TEMPERATURE COEFFICIENT
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS