ML20215E336
| ML20215E336 | |
| Person / Time | |
|---|---|
| Site: | Berkeley Research Reactor |
| Issue date: | 08/20/1964 |
| From: | Mark H CALIFORNIA, UNIV. OF, BERKELEY, CA |
| To: | Lowenstein R US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20215E220 | List:
|
| References | |
| FOIA-86-811 NUDOCS 8612220154 | |
| Download: ML20215E336 (2) | |
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C Attention:
Mr. Richard Silver Db 0 Rf O
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Dear Mr. Silver:
'S i The following information is supplied as Amendment No. 1 to our Application for a Construction Permit Relating to a Class 104 Facil-ity License for a Nuclear Reactor at the Berkeley Campus of the University of California, Berkeley, California (Ref. Docket 50-224).
As stated in the previously submitted " Reactor Safety Analysis":
"A horizontal seismic design coefficient of 0.20 g with a 33 per cent increase in allowable stresses has been adopted for the TRIGA Mark III reactor structure.
In order to provide additional safety in the design of the structure as a whole, critical areas (areas in which a failure could cause a loss of water from the reactor pool) will be designed with a higher horizontal coef ficient of 0.30 g with a 33 per cent increase in allowable stresses."
Based on this criteria, the core and support structure have been designed to the 0.20 g value.
The calculations for this condition took the following form:
- 1) The reactor tank full of water (but without the core and support structure) was analyzed to determine the response to a 0.2 g horizontal force.
The result was a calculated
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frequency response for the tank water.
- 2) The core and support structure in the reactor tank (without water) were analyzed to determine the response to a 0.2 g horizontal force.
It was found that the ma.jor part of the weight acts at the lower end of the support structure with conditions approaching that of a pendulum.
Damping is provided by the restraining force through the coupling to the bridge.
A frequency response was determined.
- 3) The core and support structure were analyzed in the reactor tank (with water) for a coupled response.
The maximum stress was calculated to be 18,400 psi.
The yield stress on non-welded 6061-T6 aluminum is 35 to 40,000 psi, giving a safety factor of roughly 2 over-8612220154 861216
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(.2 Mr. Robert Lowenstein August 20, 1964 the calculated stress.
The maximum amplitude of core motion is about 3 inches.
For your reactor conditions, it was concluded that the period of the reactor core and support structure in water does not attain reso-nance with the water in motion.
Even if resonance i
were to occur and the structure exceeded the yield stress, no f ailure would occur because as the material yields, it would relieve the stresses and unsynchronize the i
response of the structure with the water in the tank.
Very truly yours, h
Hans Mark l
Chairman, Department of Nuclear Engineering HM: LR: bj d State of California)) ss.
County of Alameda
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Before me personally appeared to me known to be the person described in the above application, who signed the foregoing instrument in my presence, and gade oath before me to the allegations set forth therein, on the g/y -/- day of fm,//pg 1964.
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