CONTROLLED SAFETY TEST ROD WITHDRAWAL TRANSIENTS (POWER RANGE). CORE I, SEED 2, EFPH 2248. Section 2. Test Results T-612393-C Page: 4 of 44
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TEST RESULTS
DLCS 2760201
T-612393-C
CONTROLLED SAFETY TEST ROD WITHDRAWAL TRANSIENTS
(Power Range)
CORE I SEED 2
Purpose
To obtain data on the dynamic response of the Reactor Plant to various power range
control rod withdrawal transients. It was also intended to compare these results
with simulator studies in order to verify analytical models and techniques used to.
predict reactor response.
Conclusions and Recommendations
. The data recorded during the test indicated that the Reactor Plant generally re-
sponded in the manner predicted when subjected to various power range withdrawal
transients. These transients were effectively curtailed by the negative tempera-
ture coefficient without exceeding any plant limitations.
The value of the temperature and pressure coefficients at the time of the test was
approximately -1.54 x 10~ op/F and +2.5 x 10 op/psi, respectively. The temper-
ature coefficient was obtained from DLCS 1510210 which was. performed September,10;
1960. The pressure coefficient was obtained from DLCS 1510109 performed April 25,
1960. It was assumed that the change in pressure coefficient was minor with addi-
tional EFPH.
A comparison of the simulator studies and the test results indicate that in general,
the transients observed were more severe and had less measurable differences between
the 20, 40 and 60 percent power runs than those transients predicted. The only ex-
ception to the latter statement was the peak average power level which showed dis-
tinct differences between the 20, 40 and 60 percent power runs.
In making an overall comparison consideration must be given to the differences be-
tween the conditions assumed in making the simulator studies and those which actu-
ally existed during the test. These differences are:
1.. A lower negative temperature coefficient value for the core than that used
for the studies.
2. A slower rate of reactivity insertion during the test.
3. A lesser maximum amount of inserted reactivity during the test giving re-
sultswhich covered only a po-rtion of the simulator curves.
4. The test was run with all four reactor coolant pumps operating and the
studies were made with three pumps.
-l-709 02
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CONTROLLED SAFETY TEST ROD WITHDRAWAL TRANSIENTS (POWER RANGE). CORE I, SEED 2, EFPH 2248. Section 2. Test Results T-612393-C, report, April 20, 1961; Shippingport, Pennsylvania. (https://digital.library.unt.edu/ark:/67531/metadc866835/m1/4/: accessed April 24, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.