ML19322B956

From kanterella
Jump to navigation Jump to search
Reviews Calculated Fast Neutron Exposure of Reactor Vessel. Thickness & Location of Thermal Shield Adequate
ML19322B956
Person / Time
Site: Oconee  Duke Energy icon.png
Issue date: 05/18/1967
From: Pawlicki S
US ATOMIC ENERGY COMMISSION (AEC)
To: Long C
US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 7912191042
Download: ML19322B956 (1)


Text

.

C. G. Long, Chief. Beester Freject Branch #2 Divisime of Eeacter Li May 18* 1967 TIES:

R. C. DeToung.

Containment &

Camponent Techselegy Branch, DEL

5. 3. Pawlicki, Castainment & Campement Techselogy Branch, Divistaa of Beacter Licensing OcosEE ACES BEFORT = EEUTEM EXPOSUEE OF IRACTOR TESSEL CM:TB: DEL:5SP IT-22
[C W

-SD

.2 7 )

We have revisanths calanlated fast mentres exposure of the ocomme reactor vessel and the corresponding shift in the EDE temperature.

The reported e integrated fast (I>1 Mov) mestres azposure of the vessel of 3 x 1

, and the estimated NDE temperature shift of 260*F, should met cause any significant operatiemal restrictimas during proposed life of the plant.

1I The neutros exposure of the vessel of 3 x 10 was calculated ever a 40 year life of the vessel using an 80 percent Isad faster and the nazi-mae==ial peak-to-everage power ratio of 1.7.

The calesistions were performed using a transport code,TWIC, which is sa Sa code designed to solve the one-dimensional transport equation in cylindrical coordinates.

We de not consider the esiculational mothed employed to be entirely satis-factory, mainly because saly four aestm emergy groups were used to describe the mestros emergy spectrum, and only four intervals were used in the s calculations to describe the angstar segmentation of the flux.

e Nevertheless, a sufficiently high safety faster has been applied to the calculations to make them conservative. We reached this comelusion after consideration of the Ocesse plant core size, power density, and the inner diameter of the reactor vessel.

We have reviamed the thiakness and location of the thermal shield inside the reactor vessel and have found it adequata.

With respect to the serveillasca program for the reactor vessel meterial, we have asked the applicant to provide as with the type of neutros fluz moeiters skick will be used in the irradiation capsules, and with the method skick,will be employed to determine mestros flua of the irradiation samples.

ec:

3. Levine

~

It Suppl D

OY[

E. Crimes DRL Reading k

bec:

R. C. DeYoung ADRS Reading S. S. Pawlicki C&CTB Reading 1

CSCTBlDRL x [CBCTR/UtL omer >

7 n.

...f.

$URNAME>

....._15./p/67 5/18/67 om

-c-~~

-__,n,.._,..,

4912191092

.