High Temperature Leak Characteristics of PCV Hatch Flange Gasket Pages From C142449-02K

8/2/2019 High Temperature Leak Characteristics of PCV Hatch Flange Gasket Pages From C142449-02K

1/12

Lee, Richard .From:Sent:To:Subject:Attachments:

Powers, DanaWednesday, April 06, 2011 8:52 AMLee, RichardHead Seal LeakagePCV Tests Japanese (2).pdf

Richard, Attached is some information on the head seal of Japanese reactors. I will have to get back to myoffice to find more. Radiation causes crosslinking that makes the polymer stiff. Note failure (leakage) occursfaster in steam than in nitrogen. Dana

I 1(~30


2/12

-Ib 375Nuclear Engineering and Design 145 (1993) 375-386North-Holland

forOhio

High-temperature leak-characteristicsof PCV hatch flange gasketKatsumi Hirao a, Toshiyuki Zama a, Masashi Goto b, Yoshihiro Naruse b, Koichi Saito c,Takuro Suzuki d and Hiroyuki Sugino CI Tokyo Electric PowerCompany, Tokyo, Japanb Toshiba Corporation,Yokohama, Japanc HitachiLtd, Hitachi,Japand HitachiEngineering Co., Ltd., Hitachi,JapanIshikawajima-HarimaHeauy IndustriesCo., Ltd, Yokohama, Japan

Received 9 July 1993

Small-model tests were performed to examine the integrity of the containment flange gasket in a severe accident. Duringa severe accident, containment structures suffer slow pressurization at relatively high temperatures. A realistic understand-ing of containment performance in such conditions is a major concern in developing an accident management strategy. Thispaper describes the results of experiments on the sealing capability of flange gaskets at high pressures and hightemperatures. Silicone-rubber gaskets, which are used as the sealing material in BW R plant primary containment vessels(PCV) in Japan, were examined in small-model tests. The gaskets show sufficient sealing capability up to 225'C at 20kgf/cm 2 . When applying the leakage characteristics specified in this paper to codes for severe accidents, the results shouldbe examined carefully based on realistic heattransfer phenomena.

1. IntroductionThe PCV is an important structure preventing re-lease of radioactive materials from a nuclear power

plant into the environment. W e decided to study theintegrity of PCV during severe accidents after theaccidents at TMI-2 and Chernobyl. Scale models (1/8and 1/32) of a steel PCV have been pressurized by airto rupture; a 1/6 scale model of a concrete PCV hasalso been tested [1,2,3,4]. Leak tests of many types ofgaskets at flanges and of full-scale personnel air lockshave been performed successfully [5,6,7,8]. There aremany reports from such tests.We formed a study group to investigate the high-temperature leak characteristics of gaskets in nuclearpower plants and to establish the integrity of the PCV.This program was divided into three phases. Phase 1Was composed of a survey of literature and test results.In phase 2, we conducted component tests and small-

Workshop on Containment Integrity [9]. The results ofphase 3 were reported in SMiRT 11 [10]. In the nearfuture, these reports will contribute to assessment ofPCV integrity for licensing purposes.This report presents the details of phase 2 in whichthe following two tests were conducted at high temper-atures:(1) Component test(2) Small-model test.

Item (1) wa s used to clarify the gasket materialproperties at high temperatures, and Rein (2) evaluatedthe high-temperature leak characteristics and obtainedthe minimum temperature and pressure at which theflange gasket started leaking.

2. Tests


3/12

t-2

Fig. 1 Dimensions of test specimen for tensile test.

and irradiation. In the small-model test, the pressuriz-ing medium, temperature, tightness, pre-irradiationwith y-rays and configuration of the seal were chosenas test parameters.

E(3at

Ctt. CflGt

CI-.

50

A--& Irradiated~inteam

0-datdn ta

U IUU 2UUTemperature (r-)2.1. Component test Fig.,2. Effect of temperature to tensile strength.

The test pieces were made of silicone rubber withthe same specifications as gaskets used in actualplants.We prepared two types of specimen: a normal and anirradiated one (80 Mrad). This condition is referred toas the electrical penetration specification. We pre-pared three sets of specimens for each test case.2.1.1. Tensile test

We tested the tensile strength of the specimens athigh temperatures and obtained the load-deformationcurve for silicone rubber.(1) Test procedures

Figure 1 shows the specimen configuration. The testtemperatures were room temperature, 150 0C, 200'C,and 250'C. Each test specimen was held for 1 hour atthe test temperature. Specimens were then pulled fromeach side and the elongation was measured. We testedeach specimen type three times under the same condi-tions.(2) Results

The results are shown in Figs. 2 and 3. The tensilestrength of the non-irradiated specimen at 150"C ishalf that at room temperature (Fig. 2). It becomesconstant from 150TC to 200TC and then decreases above200'C. In contrast, the tensile strength of the irradi-ated specimens is one-quarter that of the non-irradia-ted specimens at room temperature, and then slowlydecreases up to 250'C. As shown in Fig. 3, the elonga-tion of the non-irradiated specimen is similar to itstensile strength.. However, the elongation of the irradi-ated specimen is twenty times less than that of thenon-irradiated specimen at room temperature. Theelongation of the non-irradiated specimen is 300% at250'C.

2.1.2. Compression testWe conducted these tests to investigate the resis-

tance characteristics of the sealing material at hightemperatures.(1) Test procedures

The test'specimen configuration is shown, in Fig. 4.The testing temperatures were room temperature,150-C, 200-C, 250-C, 300"C, and 350'C. The test speci-men wa s compressed to 75% of its original height. Itwa s held at the test temperature.for 22 hours and thenthe residual strain was measured. We tested threespecimens under the same conditions.(2 ) Results

The results are shown in Fig. 5. The residual straingradually increases up to 150'C. Above this tempera-

10000-0 Non-IrradiatedIn Air&--, Non-Irradiated.In Steam0- -0 Irradiatedin Air&--A Irradiatedjn Steam0 "

C 5000}

0 w

Fig. 4. Dimen

ture, it incremen reachesreaches 100%the irradiatemen was alr22. Small-m

We consid(1) leakage(2) leakage con the seconthe test specia groove-ancused widelywas 250 mmThe test gasused in actua

Ji

100

- 50

0

CTemperature ('C)Fig. 3.Effect of temperature to elongation ratio. Fig. 5


4/12

I . II

0813 Diablo Canyon briefs HOOs that they have assumed a 'stranded plant' status (i.e. all inboundtraffic to the site has been suspended). Authorities ordered local evacuations.0817 Still on R4/EDO call: OIP went through situation in Japan. OIP extended offers to Japan to help

then in any way we can with their emergency response capabilities. Plants in Japan have all lostpower and are in station backout.0823 Still on r4/EDO call: OIP mentions that we expect a significant amount of press inquiries. Next

call is scheduled for 1100 EST.0824 Still on R4/EDO call: NRC .agrees to possibly reconsider later whether to reevaluate agency

posture.0825 Still on R4/EDO call: Brian McDermott suggests we 'set up ' operations center to help the

Japanese visitors.0827 Still on R4/EDO call: Eric Leeds suggests that the call reconvene around the time that the

tsunami is scheduled to hit the CA coast at 20am CST.0930 ENAC information retrieved by HOO says all units at Fukushima Daichi and Daini sites shutdown.0942 Bridge convened early (ET-6110) by Mike Weber and Brian McDermott with Elmo Collins added.Mike Weber suggests that because of the excessive interest by both the Chairman and externalagencies that the agency go to a monitoring mode where possibly R4 leads for US concerns and

HQ take the lead for international activiites.0945 Elmo Collins suggests that agency enter monitoring mode. NRR Eric Leeds concurs.0946 NRC enters monitoring mode.


5/12

K_Hiraoet at / High-temperature eak-characteristics 379

"Testlec

20

15C)

0CD3 1

0 Tightness Value 0.0mmrA Tightness Value 0.8mm-3 Tightness Value 1.6mmv Tightness Value 2.5mm* L Y No Leakage

II(0700)Flange

0 1010( 200 MIDTemperature (C)Fig. 10. Effect of temperature to leak starting pressure(Semi-Round Type, steam).

tion. Our test parameters are shown in Table 1. Pres-sure and temperature were measured using pressuregauges and thermocouples. Gaskets were checked visu-ally after the tests.2.2.2. Test resultsa. Semi-round gasketThe results are shown in Tables 2 and 3. Therelationship between the leak pressure an d tempera-ture is shown in Figs. 9 and 10.

Fig. 8. Test facility of Groove-and-Tongue Type (case of N2gas).

02

'If

0)_j

(a) Leak pressurePressurized by N2 gas: In the non-irradiated speci-mens, leakage did not occur up to 275C at the lowest

tightness level D1 (Table 2). At 300"C, a leak occurredaround 18 kgf/cm2 at the Dl, D2, D3 and D4 tight-ness levels. In the irradiated specimens, leakage didnot occur up to 325'C. At 350"C, a leak occurred at 17kgf/cm 2 at D1, but did not occur at D4.

Pressurized by steam: In the non-irradiated speci-mens, leakage did not occur up to 225'C (Table 3) . At2500C, a leak occurred at 20 kgf/cm 2 at D1, but noleak was found at D2. In the irradiated specimens, noleak was found at DI until 300 0 C. At 325"C, leakageoccurred at 17 kgf/cm 2 at DI, but not at D4.(b) Changes in propertiesPressurized by N2 gas: In the non-irradiated testspecimens, we observed no significant changes in thematerial properties of the test specimens below 175C.At 250C, we found small external deformations (Fig.11). At 300'C, each test specimen regardless of tight-Temperature (C)Fig. 9. Effect of temperature to leak starting pressure (Semi-

Round Type, N2 gas). ness wa s pushed ou t through the gap between the

I -


6/12

380 0KHiraoet al . / High-temperatureleak-characteristics

Fig. 11. Tested specimen after cooled down (250'C, Semi-Round, N2 gas, non-irradiated).

Table 4Leak startinIrradiation

Nonirradiated

Irradiated

@: No leakValue In Ta

upper andwas deformOne part o3250 C andat each dwere foundspecimensthe leak libecame mto the upspecimen force at hiing to roomThere Werenon-irradiadeformatiothat of th3250C, thespecimen amen at D4

Table 5Leak startinIrradiation

Nonirradiated

Irradiated

@: No leakValue In Taig. 12. Tested specimen after cooled down (2250C, Semi-Round, steam, non-irradiated).


7/12

I

K Hirao t aL / High-temperature eak-characteristics 381Table 4Leak starting pressure of Groove-and-Tongue Type (pressured by N2 gas)Irradiation Gasket Water N2Tightness 20*C 20'C 175'C 250oC 275oC 300'C 325oC 350oCNo n D1 G 0 0 0 0 14 6irradiated D2 _ _ _ 0 20 7

D3 - _ _ 0 0 10D4 G- _ _ 0 0

Irradiated D1 0 0 0 0 0 0 0 0D4 _ -.. @

&: No leakage.Value In Table: Pressure of leakage start (kgf/cm2 ).

upper and lower flange to the leak line; each specimen Pressurized by steam: We observed large deforma-was deformed and resembled a sedge-hat in shape. tions in the non-irradiated specimens. The materialOne part of each test specimen failed significantly. At properties became softer after cooling to room temper-325C and 350*C, the test specimens broke into pieces ature. Leakage did not occur at 225C. The top part ofat each degree of tightness, and many small cracks the specimen deformed outside through the gap ofwere found in each specimen. We found small parts of both flanges in the shape of a sedge-hat (Fig. 12). Thespecimens ranging from 1 mm to 2 mm in diameter at same tendency was observed at 250'C and 275'C. Inthe leak line. At 350'C, damage to the test specimens the irradiated specimens, the deformation was lessbecame more significant because the specimens stuck than that of the non-irradiated specimens at tempera-to the upper flange. At 325C and 350'C, the test tures below 325'C.specimen material became soft and lost its restraining b Groove-and-tongue gasketforce at high temperature. It became brittle after cool- b. re-are g a bleting to room temperature. a The results are shown in Tables 4 and 5. Figures 13There were few differences between the irradiated and and 14 show the relationship between the leak pres-non-irradiated specimens up to 250C. At 275"C, thedeformation of the irradiated specimen was less than (a) Leak pressurethat of the non-irradiated specimen. At 3000C and Pressurized by N2 gas: In the non-irradiated speci-325C, the tendency was the same. At 350C, the test mens, leakage did not occur up to 300'C (Table 4). Atspecimen at DI broke into small pieces but the speci- 325"C, a leak occurred at 14 kgf/cm 2 at the DI tight-men at D4 kept its original form. ness level, and at 20 kgf/cm2 at D2. No leak was found

Table 5Leak starting pressure of Groove-and-Tongue Type (pressured by steam)Irradiation Gasket Steam

Tightness 175C 250'C 275C 300C 325C 350CNo n DI @ @ 20 5 4irradiated D2 .... 8 6

D3 .... 0 10D4 - - - 0 10

Irradiated DI - _ _ 0 -D4 ......0: No leakage.Value In Table: Pressure of leakage start (kgf/cm2 ).


8/12

r

382 K. Hiraoet aL / High-temperatureleak-characteristics

o Tightness Value 0.75mmtm A Tightness Value 1.5 mm_Z T5ghtness Value 2.25mm

7 Tightness Value 3.0 mm0 A * v No Leakage

10 -

5-at0 100 200 300

Temperature (C)Fig. 13. Effect of temperature to leak starting pressure(Groove-and-Tongue Type, N2 gas).

at D3 and D4. In the irradidated specimens, leakagedid not occur up to 350'C at D1. Neither was a leakfound in an extra test at 3750C.

Pressurized by steam: In the irradiated specimens,no leakage was found up to 300C (Table 5). At 325C,leakage was found at 5 kgf/cm 2 at D1, and at 8kgf/cm 2 at D2, but not at D3 and D4. At 350'C,leakage was found at 4 to 10 kgf/cm 2 at D1 to D4. In

E.kA13IV

Tightness ValueTightness ValueTightness ValueTightness Value v No Leaka

0 0@ U0.75mm1.5 mm2.25mm3.0 mm

ge~-10

5)_j

0 100 200 300Temperature ('C)

Fig. 14. Effect of temperature to leak starting pressure(Groove-and-Tongue Type, steam).

the irradiated test specimens, no leakage was found upto 3250C at 13.(b) Change of properties

Pressurized by N2 gas: In the non-irradiated testspecimens, we found no change except a tongue traceup to 300'C (Fig. 15). At 325C, we found cracks in themain part of specimens. Th e ring form was maintained

when nocurred, paleak line. Aand the teable. Testcame verypieces.Few crackThey failespecimens.. Pressurspecimenswere no lbecame mcases, thewe found sin the irradated ones. tion with N

3. Discuss3.1. Mater

Th e irrlower tensgation thanstrain of th

Fig. 15. Tested specimen soon after cooled down. (300'C, Groove-and-Tongue, N2 gas, non-irradiated).


9/12

K Hiraoet aL / High-temperature eak-characteristics 383when no leak occurred (Fig. 16). When a leak oc-curred, part of one test specimen was extended to theleak line. At 350TC, we found cracks in the main partand the tendency to external deformation was remark-able. Test specimens at temperatures above 325C be-came very fragile, lost their elasticity, and broke intopieces.Few cracks were found in the irradiated specimens.They failed locally compared to the non-irradiatedspecimens.

Pressurized by steam: At 300'C, non-irradiated testspecimens were largely deformed even when therewere no leaks, and we found cracks. This tendencybecame more significant at-325C and 3500C. In thesecases, the test specimens stuck to the upper flange andwe found small broken parts. The deformation was lessin the irradiated test specimens than in the non-irradi-ated ones. This is similar to the results from pressuriza-tion with N2 gas.

3. Discussion3.1. Materialproperties

The irradiated specimens had two to four timeslower tensile strengths and 20 to 30 times lower elon-gation than the non-irradiated specimens. The residualstrain of the non-irradiated specimens increased rapidly

from 200C and reached 100% elongation at 250'C.These results prove that, in general, the upper limit foruse of silicone rubber as a sealing material is 200'C.Silicone rubber is transformed and loses its recover-ability above 250C.The irradiated specimens had greater recoverabilityat high temperatures, but fractured at 250*C. Thisshows that the specimens got harder and lost flexibility.Whether irradiated or not, silicone rubber is no t appli-cable as a sealing material above 2500C.3.2. Pressurizing medium

Leakage occurred more rapidly under steam pres-sure than under N2 gas pressure. This was observedclearly for both gasket types. This is explained by thematerial properties of silicone rubber. Silicone rubberat high temperatures and under steam pressure de-grades easily compared to that under N2 gas pressure.It becomes soft an d loses mechanical strength whichleads to leakage. It is clear that semi-round gaskets willleak easily if there is a large area exposed to high-tem-perature steam.3.3. Temperature.

We have shown that leaks occur from 275C to3000C under N2 gas pressure and from 2250C to 3000Cunder steam pressure. Similar tendencies were ob-

starting pressureti1).

e was found up

-irradiated testa tongue trace

id cracks in thewas maintained

Fig. 16 . Tested specimen soon after cooled down (325C, Groove-and-Tongue, N2 gas, non-irradiated).


10/12

384 K Hiraoet aL / High-temperature eak-characteristicsserved in both cases. As the temperature increases, theleak pressure decreases. Silicone rubber is damagedand becomes soft at high temperatures and it losesmechanical strength. The sealability of silicone rubberis lost at temperatures ranging from 2251C to 3000C.3.4. Tightness

We investigated the influence of the flange tight-ness on leakage at a high pressure of 20 kgf/cm 2. Asexpected, as the flange tightness increases, the leakpressure increases. Up to 225"C, we observed no leaksat 20 kgf/cm 2 despite the tightness level (DI, D2, D3and D4). We found leaks in some cases above 225Cand below 20 kgf/cm 2. This is explained by the mate-rial properties of the silicone rubber; damage at hightemperatures leads to loss of gasket sealability. Below20 kgf/cm 2, it is clear that the effect of flange tight-ness on leakage is minimal compared to that of tem-perature.3.5. y rays

It is known that silicone rubber changes 'and be-comes harder with irradiation. In this test, irradiated

Upper Flange Inside Ouli

gaskets became harder than non-irradiated ones. Wefound that the leak temperature of irradiated gasketswas higher than that of non-irradiated ones. Irradiatedspecimens seem to have a greater sealing capacity,because they become harder and maintain their solid-ity at high temperature, which makes the leak tempera-ture higher.3.6. Gasket type

We performed leak tests for the semi-round gasketwith a tightness value of 0 mm. In this case, the gasketonly touched the upper flange. If the gasket and flangetouch slightly, a seal effect is expected under a pres-sure of 20 kgf/cm 2 and a temperature of 225'C. This isconsidered to be an advantage of the self-sealing effectof semi-round gaskets. As shown in Fig. 17, the gasketis pushed into the groove of flange by internal pressureand maintains the seal by filling the flange gap.Th e groove-and-tongue gasket maintains a seal athigher temperatures than the semi-round gasket. Thedifference is that the gasket is flat and is pushed intothe groove locally by the tongue. The cross-section areais 30% larger than that of the semi-round type. Th epressurized area of the gasket is also different. Thesedifferences ma y account fo r the different test results.

4. Leakage assessment4.1. Leakage characteristics

From the results of this study and the results ofphase 3, we have shown that gasket leakage can beclassified into two types: (1) leakage originating fromgasket failure, and (2) leakage resulting from flangedeformation.We have shown that temperature is a governingfactor in gasket failure. Leakage assessment may beperformed as described below.(a) The effect of flange tightness on sealing is smallerthan that of temperature, so test data for eachdegree of tightness can be grouped together.(b) Leaks are more likely to occur under steam pres-sure than under N2 gas pressure. The pressurizingmedium at accidents is believed to be steam and N2gas. The results for each medium can be groupedtogether.

(c) The data for the semi-round and groove-and-tonguegasket should be grouped separately.(d) Th e relationship between the gasket failure tem-

peratursentedT=a.whereb are cMetho

(e) The wiin theness oFrom thedisplayed

E

CD

55(Dn-rest

Lower Flange

Groove-and-Tongue TypeFig. 17. Movement of gasket under inner pressure.


11/12

K Hiraoet aL / High-temperature eak-characteristics 385

ones. WegasketsIrradiatedaling capacity,

their solid-leak tempera-

ii-round gasketase, the gasket;ket and flangeunder a pres-E 25 0C. This isf-sealing effect17, the gasketternal pressure

ige gap.tains a seal atid gasket. Theis pushed intoss-section areaund type. Th eifferent. Theset test results.

perature and pressure is assumed to be repre-sented by the following equation.T=a -P+b,where T is temperature, and P is pressure. a andb are coefficients determined by the Least SquaresMethod.

(e) The width of the defined region is enhanced by 3a 'in the temperature direction considering random-.ness of the data.From the above, the region where leakage will occur is

displayed in Fig. 18.

4.2. PSA and accident management applicationsIn some previous PS A studies, local leakage causedby overheating ma y not be well considered. However,the previous PSA results do no t lose their validity

because integrated severe accident codes such asMAAP, treat the containment temperature calculationusing relatively-simple modeling, and the calculatedtemperature does not show the specific local tempera-ture. In fact, containment is not a simple onenodestructure, bu t a complex structure containing manycomponents such as shield walls, thermal insulators,

CE20

S15

a. 100)

Ca

0

o Pressured by N2 Gaso Pressured by Steam- AverageAverage 3 o

1,

i i'Io'I__ I

0 Pressured by N2 Gaso Pressured by Steam- Average-- Averaae 3 o

CGu

CO

C/)

20 I

15 I

10 I5 -i

the results ofakage can beiginating fromg from flanges a governing;ment may beling is smallerdata for eachogether.,r steam pres-e pressurizingsteam and N2in be groupedve-and-tongue

200 400Temperature (0C)a Semi-Round

600 0 200 400Temperature (0C)

b. Groove-and-Tongue600

a~- -2Ein

a)

Ca

'C3

5- ILeak AreaI0

5- IN o Leak Areaa 200 400

Temperature (C)600

c. Leak / No Leak AreaFig. 18. Leakage prediction of silicone gasket.t failure tem-

1I


12/12

386 K7Hirao l al. / High-teipipes and valves. With high local temperatures, theflange gasket temperature would be lower than that ofthe local area because of thermal radiation, or heattransfer by convection, etc. These things indicate thatcontainment heat transfer models will be important incalculating the containment response in a severe acci-dent.

Heat transfer models of interest are: (a) structure-to-structure radiative heat transfer using.realistic ra-diative heat transfer constants and (b) natural convec-tion. A realistic understanding of containment perfor-mance in a severe accident is a major concern indeveloping an accident management strategy. Whenapplying the leakage characteristics specified in thispaper to codes for severe accidents, the analyticalresults obtained by the codes should be examinedcarefully based on the effect of realistic heat-transferphenomena.

5. Conclusions(1) Silicone-rubber gaskets in a PCV can maintain

their and mechanical strength up to 200'C.(2) The pressurizing medium and temperature are

governing factors in flange sealability. Flange tightnessdoes not have a significant effect.

(3) Silicone-rubber gaskets have sufficient sealabil-ity up to 225C at 20 kgf/cm2 . This pressure is approxi-mately 5 times that of the PCV design pressure.

(4) Leakage prediction criteria can be defined re-lated to temperature and pressure.

(5) When applying leakage characteristics specifiedin this paper to codes for severe accidents, the analyti-cal results should be examined carefully based on real-istic heat-transfer phenomena.

mperature eak-characteristics Nuclear EngNorth-HollaReferences

[1] D.B. Clauss, D.S. Horshel, and T.E. Blejewas, Insightsinto the behavior of LW R containment buildings duringsevere accidents. Nucl. Engrg. Des. 100, No . 2 (1987)189-204.[2] L.N. Koenig, Experimental results for a 1:8-scale steelmodel nuclear power plant containment pressurized tofailure, NUREG/CR 4216 (1986) 1-86.

[3 ] D.S. Horshel and T.E. Blejewas, An analytical investiga-tion of the response of steel containment models tointernal pressurization, Trans. 7th International Confer-ence on Structural Mechanics in Reactor Technology,Vol. (6/4) (1983) pp. 297-304.[4] W.A. Vo n Riesemann, T.E. Blejewas, A.W. Dennis an d

R.L. Woodfin, NRC containment safety margins programfor light-water reactors, Nucl. Engrg. Des. 69, No . 2(1982) 161-167.

[5] J.T. Julien and S.W. Petters, Leak rate test of contain-ment personnel lock, Fourth Workshop on ContainmentIntegrity, Washington, D.C. (1988) pp. 1-15."[61 L.N. Koenig and C.V. Subramanian, Leakage potential

of LW R containment penetration under severe accidentconditions, Nucl. Engrg. Des. 100, No. 2 (1987)121-128.[7] D.B. Clauss, An-evaluation of the leakage potential of apersonnel airlock subjected to severe accident loads,Trans. 9th Intemrational Conference on Structural Me -chanics in Reactor Technology (1987) 147-152.[8] L.N. Koenig, Leakage potential through mechanical pen-

etrations in a severe accident environment. NUE-REG/CP-76, p. 557-568 (1986).

[9] K. Hirao, M. Goto, Y. Naruse, K. Saito, T. Suzuki and H.Sugino, High temperature leak characteristics test ofPC V hatch flanges gasket, in: Proceedings of the FifthWorkshop on Containment Integrity, NUREG/CP-0120,p. 457-463, May 12-14 (1992).[10] K. Hirao, M. Goto, Y. Naruse, K. Saito, K. Hasegawaand H. Sugino, Pressure test of the typical vessels flangeunder pressure loading, Trans. lt h International Con-ference on Structural Mechanics in Reactor Technology,J02/4, (1991) pp. 25-30.

TeofB.LSandRece

Thimpoparaimpotransthreedatabetwspecsystecond

1. IntroduThe U.

investigatito severethe ContaNational Linforced Canchoragewas a lineffects tesparameterment analof liner finstrumenthe testinfinite elemtypes.The obdevelop ascale RCC* This wor

Commissries, whiunder Co0029-5493

High Temperature Leak Characteristics of PCV Hatch Flange Gasket Pages From C142449-02K

Documents

Transcript of High Temperature Leak Characteristics of PCV Hatch Flange Gasket Pages From C142449-02K