SCOPUS 정보 검색 플랫폼

JOM

Volumn 53, Issue 7, 2001, Pages 14-17

Alloy optimization for PWR steam generator heat-transfer tubing

(3) Harrod, D L a,b Gold, R E b Jacko, R J c

a Westinghouse Electric Company (United States)

b WESTINGHOUSE ELECTRIC COMPANY (United States)

c Westing House Science and Technologies Department (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ANNEALING; CORROSION RESISTANCE; HEAT TRANSFER; HEAT TREATMENT; LIGHT WATER REACTORS; NICKEL ALLOYS; OPTIMIZATION; PASSIVATION; STAINLESS STEEL; STEAM GENERATORS; STRESS CORROSION CRACKING; TUBING;

HEAT TRANSFER TUBING; INNER DIAMETER SURFACE PASSIVATION; NICKEL CROMIUM IRON ALLOYS;

PRESSURIZED WATER REACTORS;

EID: 0035389122 PISSN: 10474838 EISSN: None Source Type: Journal
DOI: 10.1007/s11837-001-0080-1 Document Type: Article

Times cited : (48)

References (13)

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2
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3
- 0141719148
- Inconel 690: A material with improved corrosion resistance for PWR steam generator tubes
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4
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- note

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6
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7
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8
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9
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10
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11
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12
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- Constant extension rate (CERT) testing of alloy 690 and alloy 800 nuclear steam generator tubing
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- Sarver, J.M.¹

13
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- Unpublished research, Westinghouse Electric Co., LLC

* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.