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RRFM 2009 Transactions - European Nuclear Society

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the primary circuit in the central CR region, but most of it outside the primary cooling channel in the heavy<br />

water (HW) tank and its installations.<br />

control rod (CR) position [cm]<br />

40<br />

30<br />

20<br />

10<br />

first criticality with warm-cold correction<br />

'cycle 6', no stop<br />

burn up calculation at total power: 20MW<br />

'burn up'- calculation operation 'cycle 6'<br />

Picture 1:<br />

CR driveway calculated and<br />

measured. The red crosses<br />

mark the positions given by<br />

the first ‘no-stop’-operation<br />

‘cycle 6’ in 2006 of FRM II.<br />

The blue dots mark the time<br />

steps of the burn-up<br />

calculation, that gives in<br />

parallel the power distribution<br />

data as input for the<br />

thermohydraulic temperature<br />

evaluation with the code NBK.<br />

0<br />

0 10 20 30 40 50 60<br />

-10<br />

FPD [d]<br />

3 Detailed temperature evaluation for fuel plates with NBK code<br />

TUM also developed a tailor-made thermohydraulic code NBK [5][6] for the description of all relevant parameters<br />

during steady state cooling of the fuel element. It has not been used for safety evaluations where<br />

standardized routines are mandatory. However the code NBK includes details that could not be modeled in<br />

any of the very few qualified codes that were available at that time. Some of the general features of NBK are:<br />

a) Full evaluation of the thermohydraulic parameters over the whole length of the cooling channels.<br />

That means local coolant speed in the channels for the water; local pressure values, pressure drops;<br />

local heat transfer values and resulting temperatures for the water and the wall surfaces.<br />

b) Evaluation of the thermohydraulics also with differentiation over the width of the cooling channels<br />

(the channel edges are also respected). Any 2d-power profile can be regarded.<br />

The very particular features are:<br />

c) The 2d-power profiles generated at the former neutronic burn-up calculations can be used and are<br />

adjusted directly to the 2d-profile of the plates ‘meat’ layer.<br />

d) Heat transfer over the width of the plates is evaluated. This is important for the plate sides where the<br />

‘meat’ layer inside ends abruptly and sees more heat transferring aluminum around; again this is of<br />

clear effect for the ‘meat’ area of FRM II fuel plates, where the uranium density changes abruptly<br />

from 3 g/cc to the half value. There are several areas of heat transfer, the two claddings, the ‘meat’<br />

and the remaining aluminum at the plates sides as well as the edges of the cooling channels which<br />

are formed by the inner and outer core tubes. All of them are described by finite elements for the<br />

heat transfer.<br />

e) The involutes shape of the plates and channels is respected. That is, the heat transfer finite element<br />

areas in the plates follow the involute shape and are thus not exactly rectangular. Because of this the<br />

plate ‘meat layer’ sees also different channel areas left and right.<br />

226 of 455

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