ML100271835
| ML100271835 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 07/15/1970 |
| From: | Boston Insulated Wire & Cable Co |
| To: | |
| Shared Package | |
| ML093430851 | List: |
| References | |
| B904, NUDOCS 8202090377 | |
| Download: ML100271835 (12) | |
Text
EFFECT OF H 3 ON IRRADIATED RUBBER REPORT NO.
WIRE INSULATIONS B904 JULY 15, 1970 BOSTON INSULATED WIRE & CABLE CO.
65 BAY STREET BOSTON, MASSACHUSETTS 02125 820209377 820204 PDR ADOCK 05000286 P.
PDR BO SOLUTION 9D
EFFECT OF H 3 BO03 SOLUTION ON IRRADIATED RUBBER WIRE INSULATIONS REPORT NO.
B904 JULY 15, 1970 BOSTON INSULATED WIRE & CABLE CO.
65 Bay Street BOSTON, MASSACHUSETTS
INTRODUCTION It has been estimated that in the event of an accident in a nuclear power station, equipment will be showered with a water spray of 0.15 gal./min./Ft2.
This spray could vary in chemical content from a boric acid (H B03 ) solution of pH = 4 to a boric acld solution adjusted to a pH of 10 with sodium hydroxide (NaOH).
It was therefore necessary to evaluate the performance of rubber compounds as insulations and jackets for nuclear cables in the presence of these chemicals.
Since it is possible that cables involved in an accident would previously have received quite high doses of radiation, it was decided to test both unirradiated and irradiated material to a total integrated dose of 1 x 109 rads by an electron beam.
In addition, coincident conditions of pressure and temperature are also present in such an accident, so these factors were also introduced into the test.
0 CONCLUSION Bostrad 7 (CSPE), GR 853A and GR 861 (EPM) when subjected to H BO solution exhibit small changes N 3
physical properties which indicates their suitability for use in such environments.
See BIW Report No. B901 and B903A for data pertaining to other properties of these materials on wire.
0
0 3
DISCUSSION In general, the effect of aging on tensile and elongation of irradiated and unirradiated samples in pH = 4 and pH - 10 solutions was graded to the following levels of performance:
E - Excellent VG - Very Good G - Good F -
Fair P - Poor Material OR 45 OR 838 OR 789A GR 853A OR 861 OR 547C OR 847C GR 859 Cha nge Change Change Change Cha nge CSPE CSPE CaSPE EPDM EPM Neoprene Butyl Rubber Hydrin Rubber less less less less more than 10%
than 20%
than 30%
than 40%
than 40%
Unirrad.
Irrad.
F F
VG P
F G*
E VO*
VO P
VG P
P P
- Preferred materials
4 TEST PROCEDURE Two solutions were prepared; the first, a boric acid solution of pH = 4, and the second, a boric acid solution adjusted to a pH of 10 with sodium hydroxide. Three dumbell specimens
- of each compound were immersed in the 1st solution contained in an air bomb, and three were immersed in the 2nd solution. The specimens were then aged in these solutions for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at a temperature of 250OF (1210C) at 15 psi. After aging, tensile strength and elongation were measured.
Since only three irradiated dumbells of each coumpound were available for this test, the irradiated samples were only aged in the solu tion of pH 1
10 under the same conditions of temperature and pressure as the unirradiated samples.
Again, tensile strength and elongation 0
were measured after aging for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
The compounds tested were:
OR-45 (Bostrad 7)
CSPE GR-838 CSPE GR-789A CSPE GR-853A EPDM GR-861 EPM GR-547C Neoprene GR-847C Butyl Rubber GR-859 Hydrin Rubber Results The medians for the three values of tensile strength and elongation for each compound are shown in Table 1. The unaged values for both irradiated and unirradiated samples are shown for comparison.
These median values are also shown in a percentage change from the original unaged values for each compound on the attached sheets.
0
EFFECT OF BORIC TABLE 1 ACID AGING ON TENSILE STRENGTH AND ELONGATION Radiation Dose (Rads) 0 1 x 108 Compound Unaged Aged in pH 4 Aged in pH 10 Unaged Aged in pH 10 Tensile Elonga-Tensile Elonga-Tensile Elonga-Tensile Elonga-Tensile Elonga Strength tion Strength tion Strength tion Strength tion Strength tion (P.s.I.)
(M)
(P.s.I.)
(M)
(P.s.I.)
(M)
(P.s.I.)
(M)
(P.s.I.)
(M)
OR 45 2540 475 3110 400
.2700 400 2600 150 2750 112 GR 838 2160 375 2420 250 2090 325 2880 150 2940 100 GR 789A 1465 525 1520 475 1635 450 1025 50 430 36 GR 853A 1135 425 1130 575 1160 400 875 75 1100 88 GR 861 1580 300 1550 300 1520 300 1850 75 1730 88 GR 547C 2340 400 2200 350 2190 50 200 12 GR 847C 930 475 810 500 GR 859 1900 675 2060 400 2140 425 290 75
~31 P
TABLE 2 EFFECT OF BORIC ACID AGING ON TENSILE STRENGTH AND EL PERCENT CHANGE IN PROPERTIES ONOATION Radiation Dose (Rads) 0 1 x 108 Compound Unaged Aged in pH 4 Aged in pH 10 Unaged Aged in pH 10 Tensile Elonga-Tensile Elonga-Tensile Elonga-Tensile Elonga-Tensile Elonga Strength tion Strength tion Strength tion Strength tion Strength tion (P S.I)
(C)
(P.S.I.)
M (P.S.I.)
M (P.S.I.)
M (P.S.I.)
M OR 45 2540 475 f23
-16 f6.5
-16 2600
,150
+6
-25 OR 838 2160 375 412
-33
-4
-13 2880 150 44
-33 OR 789A 1465 525
+4
-10 411.5
-14 1025 50
-58
-28 OR 853A 1135 425
-1 435
+2
-6 875 75 426
+17 OR 861 1580 300
-2 0
-4 0
1850 75
-7
- 17 OR 5470 2340 400
.-6
-12 2190 50
-98
-76 OR 847C 930 475
-13 45 OR 859 1900 675 49
.-41
- 13
-37 290 75
'.9J.
Q 4
9
UNIRRADIATED UNIRRADIATED, AGED IN PH4 SOLUTION UNIRRADIATED, AGED IN PHIo SOLUTIION IRRADIATED TO 1 X 10a RADS IRRADIATED TO 1 X 108 RADS, AGED IN PH10 SOLUTION GR 4 5 GR 3B GR6GI 7001 600 7
-j 200 I00 GR859
/i".'
GR789A GRB53A
3500 3000
,2500 t2000
- U)
-j 500 z Ll I-l 1000 500 0
GR45 C-e GR 838 UNIRRADIATED SUNIRRADIATED, AGED IN PH4 SOLUTION UNIRRADIATED, AGED IN PH 10 SOLUTION SIRRADIATED TO I X 108 RADS lID IRRADIATED TO 1 X 108 RADS, AGED IN PH10 SOLUTION G R 789A csep_
GR853A
-PD t. 0 GR8GI r_- 0 0 GR547C J C-0 PIkjc GR847C 6i 3ryL-GR859 A-1 Q
V A
-]--I I KNI kx]
. 0....
- 1. - -..
- 1. 1-111- - -
I
13.0 REPORT
SUMMARY
SUMMARY
Ageing - Since all the pressure retaining mater.ials are either metals or ceramics, no significant ageing of these materials will occur during the postulated life of the plant.
Cable insulation materials and potting compounds show 40 year life on the Arrhenius plots for the normal operating temperatures.
Radiation - All materials used will readily withstand a minimum of 108 of gamma irradiation well exceeding the required 2 X 107 Rads.
LOCA - The required LOCA profile, having a maximum of 287*F was enveloped by a 340°F temperature profile in the qualification testing performed.
Ample margin was demonstrated.
Qualified Life A qualified life of (40) years from start of plant operation for the electric penetrations listed in Section 1.0 of this report has been demonstrated by test and analysis.
0/