[논문]Influence of repair welding on cyclic thermal shock behaviour of a RPV nozzle corner

Kussmaul, K.; Blind, D.; Jansky, J.

doi:10.1016/0308-0161(86)90095-5

Influence of repair welding on cyclic thermal shock behaviour of a RPV nozzle corner

The International journal of pressure vessels and piping, v.25 no.1/4, 1986년, pp.89 - 109

Kussmaul, K. , Blind, D. , Jansky, J.

Abstract ▼ AI-Helper

In piping as well as in RPV-nozzles and in surrounding parts of the cylindrical vessel shells, repeated cold water injections have been observed leading to crack initiation and subcritical crack growth.In the framework of the German Reactor Safety Research Programme, cyclic thermal shock tests have been carried out at the RPV of the decommissioned HDR (Heissdampfreaktor) near Frankfurt applying extremely conservative temperature transients. The crack propagation under access of oxygenated pressurized water was evaluated by fracture mechanics methods. The validation by non-destructive examination, as well as by destructive testing at a trepan, proved the fracture mechanics results to be conservative.The depression at the nozzle corner caused by the trepan removal has been repaired by 'temper bead' welding without stress relief heat treatment, similar to the 'half bead' technique of the ASME Boiler and Pressure Vessel Code.The subsequent thermal shock stressing (1200 cycles) under similar parameters demonstrated, with respect to the weld repair: (1) no material separation extending into the ferritic RPV-wall;(2) the quality of repair welding is comparable to the quality of the as-delivered condition manufactured in the 1960s in a more conventional manner.The positive experience derived from this work may be helpful in the future in dealing with any cases of cracking in thick-walled large diameter vessels which could require repair welding when a post-weld stress relief heat treatment is not possible.

참고문헌 (22)

VGB Kraftwerkstechnik Kussmaul 64 12 1115 1984 Rissbildungen in Speisewasserleitungen von Leichtwasserreaktoren-Ursachen und Abhilfemassnahmen
Hickling 1984 European Federation of Corrosion Conf. on Environment Sensitive Cracking Problems in Nuclear Installations Containing High-temperature Water Strain-induced corrosion cracking of low-alloy steels in LWR systems-case histories and identification of conditions leading to susceptibility
Millstone Nuclear Power Station Unit 1, Feedwater Nozzle Cladding Defects 1974
Leckage im Mantel eines Dampferzeugers im KKW Indian Point 3 Werner 1984
Gerscha Proc. IAEA Specialist Meeting on Subcritical Crack Growth German studies of cyclic crack growth behaviour
Rissfortschrittsberechnungen (3D-FE) fur die Stutzenkante des RDB bei Thermoschock und erster Vergleich mit Versuchsergebnissen Schmitt 1984
Theoretisch- numerische Untersuchung des Thermoschockproblems an Stutzenkantenrissen des RDB-Reaktordruckbehalters Krolop 1983
Kussmaul 8th SMiRT Conf. Reaction of RPV nozzle corner areas to loads consistent with operational and accident conditions
Jansky 1984 ASME PVP Conf. Pressurized thermal shock loading at nozzle corner area of HDR-RPV
Zerstorende Prufung von Stutzenkantenrissen am HDR-Stutzen A2 nach Thermoschockversuch T10.1 1984
Jansky 1985 8th SMiRT Conf. Crack growth morphology in pressure vessel and in small scale specimen under LWR conditions
ASME Boiler and Pressure Vessel Code, Section XI, Repair Procedures, IWB-4000, American Society of Mechanical Engineers, New York, 1983 edition.
Kussmaul 1983 Proc. Int. Symp. on Reliability of Reactor Pressure Components Formation and growth of cracking in feed water pipes and RPV nozzles
HDR-Thermoschockprogramm-Ergebnisse von Untersuchungen an Platten und Modellbehalter (Vorstufe der Experimente am HDR-Druckgefass) Jansky 1979
Bericht uber die Reparatur am A2-Stutzen 1982
Schweissen und Schneiden Kussmaul 28 7 250 1976 Verfahren zur Simulation der Warmeeinflusszonen von Schmelzschweissverbindungen
Ayres 1979 5th MPA Seminar Developments in welding, repair and evaluation of welded joints in component fabrication
Schweissen und Schneiden Ewald 29 10 402 1977 Einzelheiten zur Simulation des Uberhitzungszyklus in Schmelzschweissverbindungen
MPA Specification Ja/St/Na 1982
1979
Jansky 1984 10th Meeting of the DVM-Arbeitskreises Betriebsfestigkeit Betriebsbegleitende Messungen an druckfuhrenden Bauteilen
Kussmaul 1983 Trans. 7th SMiRT Conf. Safety analysis of circumferentially cracked feed water piping of light water reactors

내보내기 구분	파일저장 인쇄 메일전송
구성항목	기본정보 상세정보 관리번호, 논문명, 저널/프로시딩명, 저자 , 발행년, 권, 호, 시작페이지, 끝페이지, 발행기관 관리번호, 논문명, 대등논문명, 저자 , 저널/프로시딩명, 발행기관, 발행년, 발행언어, 권, 호, 시작페이지, 끝페이지, ISBN, ISSN, 주제분야, 키워드, 초록(한글), 초록(영문), 저자(소속기관)
저장형식	Text(ASCII format) Excel format RefWorks Direct Export RIS format (for Reference Manager, ProCite, EndNote), Scholar's Aids, Mendeley
메일정보	받는사람 (필수) @ 보내는사람 (선택) @ 제목 내용 KISTI 검색결과 이메일 서비스
안내	총 건의 자료가 검색되었습니다. 다운받으실 자료의 인덱스를 입력하세요. (1-10,000) 검색결과의 순서대로 최대 10,000건 까지 다운로드가 가능합니다. 데이타가 많을 경우 속도가 느려질 수 있습니다.(최대 2~3분 소요) 다운로드 파일은 UTF-8 형태로 저장됩니다. 파일의 내용이 제대로 보이지 않을실 때는 웹브라우저 상단의 보기 -> 인코딩 -> 자동선택 여부를 확인하십시오. ~ Text(ASCII format) Excel format

연합인증

Influence of repair welding on cyclic thermal shock behaviour of a RPV nozzle corner

Abstract ▼ AI-Helper

참고문헌 (22)

이 논문을 인용한 문헌

관련 콘텐츠

원문 URL 링크

이 논문과 함께 이용한 콘텐츠

AI-Helper ※ AI-Helper는 오픈소스 모델을 사용합니다.

선택된 텍스트