ML20084Q663

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Forwards Intergranular Corrosion Cracking of Type 304 Stainless Steel in Water Cooled Reactors & Info Needed on Intergranular Corrosion Cracking. Documents Pertinent to Future Meeting on Intergranular Cracking of safe-end
ML20084Q663
Person / Time
Site: Nine Mile Point 
Issue date: 04/07/1970
From: Cheng C
ARGONNE NATIONAL LABORATORY
To: Mcewen J
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20084P985 List:
References
01135, 1135, NUDOCS 8306130528
Download: ML20084Q663 (2)


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ARGONNE NATIONAL LABORATORY April 7,~1970 1-Mr. John E.:McEwen Assistant to the Division Director Division of Reactor Standard (Bethesda)

U. S. Atomic Energy Commission Washington, D. C.

20545

Dear Mr. McEwen:

Enclosed please find two attachments that are pertinent to the forthcoming meeting on the intergranular cracking of core spray safe-and in Nine Mile Point Reactor.

The first attachment is a paper, "Intergranular Corrosion Cracking of Type 304 Stainless Steel in Water-Cooled' Reactors." This paper reviews published literature with respect to:

(a) numerous instances of intergranular corrosion cracking of Type 304 stainless steel in water-cooled reactors (b) the various corrosion studies on intergranular cracking (c).the proposed mechanism on intergranular corrosion cracking

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The second attachment is a memorandum, "Information Needed on Intergranular Corrosion Cracking." This memorandum reviews (a) recent reactor component failures and safe-end status

~ f water-cooled reactors reported by your Division of o

Compliance (b) ' mechanical properties needed;to evaluate intergranular.

corrosion cracking aided by low-eycle and/or static.

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Since ely, L

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Craig/P.-

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CFCalgh Mate als Science Division a

l Encit' ~ Attachments'A and B (3 copies)'

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J. O'Rieley,.DivisionLof' Compliance

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.(2 copies).

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J 9700 South Cass Avenue-Argonne. Illinok AAA39 Telephone 312-739-7711 TWX 910-2MM@X LB, Argonne, Illinois h

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ARGONNE NATIONAL L'ABORATORY April 7, 1970 I

Mr. John E. McEwen f

Assistant to the Division Director Division of Reactor Standard (Bethesda)

U. S. Atomic Energy Commission Washington, D. C.

20545

Dear Mr. McEwen:

I Enclosed please find two attachments that are pertinent to the forthcoming meeting on the intergranular cracking of core spray safe---

end in Nine Mile Point Reactor.

}

.y The first attachment is a paper, "Intergranular Corrosion Cracking of Type 304 Stainless Steel in Water-Cooled Reactors." This 1

paper reviews published literature with respect to:

3 (a) numerous instances of intergranular corrosion' cracking of Type 304 stainless steel in water-cooled reactors i

(b) the various corrosion studies on intergranular cracking (c) the proposed mechanism on intergranular corrosion cracking The second attachment is a memorandum, "Information Needed on Intergranular Corrosion Cracking." This memorandum reviews (a) recent reactor component failures and safe-end status of water-cooled reactors reported by your Division of

]

Compliance (b) mechanical properties needed to evaluate intergranular corrosion cracking aided by low-cycle and/or static stresses Sincerely,

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htW' f 1c~l l

Craig. Cheng O

CFC:Igh Materials Science Division Encl: Attachments A and B (3 copics) cc:

J. O'Ric1cy, Division of Compliance (2 copico).

0700 South Car,s Avenue, Arc,onno. !!!inois 60439 Tc!cphonc 312-730-7711 TWX 910-253-3282 WUX LB. Argonno. til:nois L

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