ML100271835

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Effect of H3 BO3 Solution on Irradiated Rubber Wire Insulations.
ML100271835
Person / Time
Site: Indian Point Entergy icon.png
Issue date: 07/15/1970
From:
Boston Insulated Wire & Cable Co
To:
Shared Package
ML093430851 List:
References
B904, NUDOCS 8202090377
Download: ML100271835 (12)
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Text

EFFECT OF H 3 BO SOLUTION ON IRRADIATED RUBBER WIRE INSULATIONS REPORT NO. B904 JULY 15, 1970 9D BOSTON INSULATED WIRE & CABLE CO.

65 BAY STREET BOSTON, MASSACHUSETTS 02125 820209377 820204 PDR ADOCK 05000286 P. PDR

EFFECT OF H3 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 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 Cha nge less than 10%

VG - Very Good Change less than 20%

G - Good Change less than 30%

F - Fair Change less than 40%

P - Poor Cha nge more than 40%

Material Unirrad. Irrad.

OR 45 CSPE OR 838 CSPE F F OR 789A CaSPE VG P GR 853A EPDM F G*

OR 861 EPM E VO*

OR 547C Neoprene VO P OR 847C Butyl Rubber VG P GR 859 Hydrin Rubber 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 10 under the same conditions of 1

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

P TABLE 1 EFFECT OF BORIC 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 12 475 --- 810 500 ------ --

GR 847C 930 GR 859 1900 675 2060 400 2140 425 290 75

~31

TABLE 2 EFFECT OF BORIC ACID AGING ON TENSILE STRENGTH AND EL ONOATION PERCENT CHANGE IN PROPERTIES 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 (P S.I) tion (C) Strength (P.S.I.) tion M Strength (P.S.I.) tion M Strength tion Strength tion (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.

4 9 Q

UNIRRADIATED 7001 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 600 7

-j 200 I00 GR789A GRB53A GR6GI GR859 GR 4 5 GR 3B ' ,,,,,

/i" .'

3500 UNIRRADIATED SUNIRRADIATED, AGED IN PH4 SOLUTION UNIRRADIATED, AGED IN PH 10 SOLUTION SIRRADIATED TO I X 108 RADS 3000 lID IRRADIATED TO 1 X 108 RADS, AGED IN PH10 SOLUTION

,2500 t2000

  • U)

-j 500 z

I-l Ll 1000 500 0 V A -]--I I KNI kx]

GR45 GR 838 G R 789A GR853A GR8GI GR547C GR847C GR859 C-e csep_ -PD t. r_- 0 0 J C-0 PIkjc 6i3ryL- A-1 0 Q

. ... - ... -. " . - - - .. .. . 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.

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