REACTIVITY ABSORBED BY XENON-135 IN THE SRE
Technical Report
·
OSTI ID:4192368
The measurement and calculation of the reactivity absorbed by Xe/sup 135/ as functions of time after shutdown for the SRE are described. The measured transient was obtained from critical shim rod configurations. The calculated transient was based on the change in thermal utilization caused by the change in xenon concentration, assuming that the other parameters in k/sub eff/ remain constant. The xenon concentration was calculated prior to shutdown. The varying reactor power was approximated in 4-hr steps to obtain the concentration present when the power was first reduced to zero. The subsequent concentration was obtained from the radioactive decay law. The measured and calculated transients agreed within 0.14% delta k/k. The calculational technique was applied to various positive and negative step changes in power so that the reactivity absorbed by xenon can be estimated for many reactor conditions. After the reactor scrams from nominal full power, the excess reactivity required for xenon compensation is 2.0% delta k/k. A 4day waiting time after shutdown is required before the reactivity worth of reactor components can be measured with an accuracy of 0.001% delta k/k without compensating for xenon. (auth)
- Research Organization:
- Atomics International Div., North American Aviation, Inc., Canoga Park, Calif.
- DOE Contract Number:
- AT(11-1)-GEN-8
- NSA Number:
- NSA-14-008285
- OSTI ID:
- 4192368
- Report Number(s):
- NAA-SR-4328
- Country of Publication:
- United States
- Language:
- English
Similar Records
Calibration of the SRE Shim Rods by the Oscillation Method
PWR PEAK XENON REACTIVITY
Compatibility Analysis on Existing Reactivity Devices in CANDU 6 Reactors for DUPIC Fuel Cycle
Technical Report
·
Mon Oct 31 23:00:00 EST 1960
·
OSTI ID:4097225
PWR PEAK XENON REACTIVITY
Technical Report
·
Sat Nov 30 23:00:00 EST 1957
·
OSTI ID:4331102
Compatibility Analysis on Existing Reactivity Devices in CANDU 6 Reactors for DUPIC Fuel Cycle
Journal Article
·
Tue Mar 14 23:00:00 EST 2000
· Nuclear Science and Engineering
·
OSTI ID:20804626