Mh. Chun et Yh. Ryu, AN EXPERIMENTAL AND THEORETICAL THERMAL-ANALYSIS OF A SIMULATED CANDU37-ELEMENT SPENT FUEL BUNDLE WITH AIR BACKFILL, Annals of nuclear energy, 25(15), 1998, pp. 1253-1262
Using a thermal mock-up of a simulated CANDU 37-element spent fuel bun
dle within a fuel basket, a series of experiments was performed to obt
ain the maximum fuel rod temperature along with the radial and axial t
emperature distributions within the fuel bundle. The main purpose of t
hese experiments was to compare the data with the predictions made by
the use of MAXROT code developed earlier. A total of 48 runs were made
with 8 different power input to the 37-element heater rod bundle rang
ing from 5 to 40 W while using 6 different band heaters power from 0 t
o 250 W (to maintain the basket wall at a desired boundary condition t
emperature) at the steady state. Comparisons between the measured and
predicted maximum fuel rod temperatures of the simulated CANDU 37-elem
ent spent fuel bundle for all 48 tests show that the MAXROT code sligh
tly over-predicts and the agreement is within 2.8% and mean deviation
is 3.2 degrees C. From this result, it is concluded that the MAXROT co
de can be used in the second step of the two-step thermal analysis met
hod proposed earlier to obtain the maximum fuel rod temperature of the
CANDU 37-element spent fuel bundle within a fuel basket in a given sp
ent fuel dry storage canister with an uncertainty of about 2.8%. (C) 1
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