• 제목/요약/키워드: 대형단조품

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유한요소법을 이용한 Ti-l5V-3Cr-3Al-3Sn 합금의 대형단조품 후방압출 공정설계

  • 정덕진;이종억;이용연;심인옥
    • 한국추진공학회:학술대회논문집
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    • 한국추진공학회 1998년도 제11회 학술강연회논문집
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    • pp.17-17
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    • 1998
  • 1970년대에 개발된 Ti-15-3 합금은 상온에서 우수한 성형성을 가지고 있어 Ti-6-4 합금보다 성형 공정을 대폭 감소시킬 수 있어 생산비용을 크게 감소시킬 수 있는 장점이 있는 합금이다. 또한, 냉간 성형성이 우수하고 강화 범위가 폭넓기 때문에 항공기의 프레임, 항공기 압력 용기 및 고장력 유압 튜브 등에 많이 사용하고 있으나, 열간 성형성이 Ti-6-4 티타늄 합금보다 좋지 않기 때문에 이제까지의 적용 분야는 판재 성형 등의 한정된 분야에만 적용되어 오고 있는 실정이다.

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모델링재료를 이용한 축대칭형 돔형상의 폐쇄단조 성형 연구 (I) (An Experimental Study on Forming an Axi-Symmetric Dome Type Closed-Die Forging Product Using Modeling Material(I))

  • 이근안;임용택;이종수;홍성석
    • 대한기계학회논문집
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    • 제16권11호
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    • pp.2082-2089
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    • 1992
  • 본 연구에서는 모델링재료를 이용한 AISI4130축대칭 도움형상의 열간 단조 공 정 설계 방안을 이룩하기 위한 실험을 수행하였다. 본 실험에 사용된 모델링 재료는 Van Akan International사 제품의 Plastalina를 이용하였다. 모델링재료와 실제 재 료 사이의 상사성을 검토하기 위해 압축실험을 수행하였는데 압축 실험시 모델링재료 와 평다이 사이의 마찰력을 줄이기 위해 베이비파우더, 휴지, 바셀린, 테프론테잎 등 을 이용하였으며 램 속도, 온도, 그리고 변형률도에 따른 응력 변화를 검토해 보았다. 열간 공정시에 수반되는 금형과 공작물 사이의 마찰력을 알아보기 위해 앞에 열거한 윤활제를 이용한 링실험을 수행하여 전단마찰계수(m) 값의 변화를 알아보고 폐쇄단조 시 주요한 설계방안을 검토하기 위해 플래쉬를 갖는 폐쇄단조 실험을 수행하였다. 이 실험에서는 폐쇄단조시 중요한 설계변수 중의 하나인 플래쉬 두께 대 폭비, 플래쉬 부를 통한 체적손실, 그리고 원기둥모양의 초기 단조 시편 형상비 등에 따른 설계방안 을 검토하여 기존 참고문헌에 나와 있는 결과들과 유사성을 검토하였다. 이와같은 실험 결과를 체계적으로 확립하고 고강도강 대형 단조품생산에 필요한 단조하중 예측, 예비성형체 설계, 성형성 연구등에 대한 응용성을 검토하고자 한다.

대형 압력용기 단강품의 자유단조 (Open Die Forging of Steel Forgings for the Large Pressure Vessel)

  • 김동권;김재철;김영득;김동영
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2003년도 춘계학술대회 논문집
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    • pp.756-759
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    • 2003
  • Steam Generator is one of the most important structural part of nuclear power plant. It is manufactured by welding process of various steel forgings such as shell, head, torus and tube sheet. These steel forgings have been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced open die forging status and investigated forging method of the ultra large steel forgings which is used for the steam generator of 1000MW nuclear power plant. For the same thing. the type of steel forgings consisting steam generator is classified by shell, head, torus and tube sheet. And corresponding forging processes of the steel forgings have been investigated.

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대형 튜브시트 단강품의 자유단조 (Open Die Forging of Steel Forgings for the Large Tubesheet)

  • 김동권;김재철;김영득;김동영;김정태
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2004년도 추계학술대회논문집
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    • pp.333-337
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    • 2004
  • Steam Generator is one of the most important structural part of nuclear power plant. It is manufactured by various steel forgings such as shell, head, torus and tubesheet. These steel forgings have been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the open die forging process and manufacturing experience of large tubesheet forgings which will be used for the steam generator of 1,400MW nuclear power plant.

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원자로용 대형 헤드 단강품의 자유단조 (Open Die Forging of the Large Head Forgings for Reactor Vessel)

  • 김동영;김영득;김동권
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2005년도 춘계학술대회 논문집
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    • pp.397-400
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    • 2005
  • Reactor Vessel is one of the most important structural part of nuclear power plant. It is manufactured by various steel forgings such as shell, head and transition ring. Head forgings has been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the open die forging process and manufacturing experience of large head forgings which cant be used for the reactor vessel of 1,000MW nuclear power plant.

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대형 단조품 코깅 공정의 기공 압착 인자에 대한 연구 (A Study on the Parameters Contributing to the Void Crushing in the Cogging Process of Large Forged Products)

  • 송민철;권일근;박연구
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2007년도 춘계학술대회 논문집
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    • pp.127-130
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    • 2007
  • Effect of the forging process parameters on the void crushing is the cogging process has been studied in order to find the most effective factor. The Process parameters used for this study are die width ratio, reduction ratio and pre-cooling time before cogging process. Void crushing analysis about the selected process parameters was carried out using FE analysis. The results of FE analysis were evaluated by Taguchi method. It was found that the efficiency of void crushing increases with an increase in the values of all selected process parameters and the principal factor controlling the void crushing was identified as the reduction ratio.

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대형 주.단조품의 온도 및 조직변화 예측에 관한 연구 (On prediction temperature and microstructure change in large cast-forged product)

  • 이명원;이영선;이승욱;김상식;문영훈
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2009년도 추계학술대회 논문집
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    • pp.414-419
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    • 2009
  • Good control of thermal energy helps to increase characteristics and eliminate defects of large cast-forged part, such as large sized forged shell. Thermal energy control is a important factor. We have studied about forging process and after heat treatment process by FEM simulation. There are three ways of process. Changes of temperature and microstructure for forged shell were predicted according to temperature declination in large cast-forged product. So we will be able to choose the proper time from heat treatment conditions by FEM simulation.

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증기발생기용 대형 단강품의 자유단조 (Open Die Forging of the Large Steel Forgings for Steam Generator)

  • 김동권;김재철;김영득;김동영
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2003년도 추계학술대회논문집
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    • pp.39-42
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    • 2003
  • Steam Generator has been manufactured by welding process after partial manufacturing of various steel forgings such as shell, head and tube sheet. Usually, these steel forgings are made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced open die forging development status of the large steel forgings which is used for the steam generator of 1,400MW next generation nuclear power plant.

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대형 단조품 코깅 공정의 기공 압착 인자에 대한 연구 (A Study on the Parameters Determining the Void Crushing Ratio in the Cogging Process of Large Forged Products)

  • 송민철;권일근;박연구
    • 소성∙가공
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    • 제16권7호
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    • pp.502-508
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    • 2007
  • Effect of the process parameters of the cogging process on the void crushing has been studied in order to identify the most effective factor. The process parameters considered in this study are die width ratio, reduction ratio and pre-cooling time before cogging process. Void crushing analysis with the selected process parameters was carried out using FE analysis. The results of FE analysis were evaluated by Taguchi method. It was found that the efficiency of void crushing increases with an increase in the values of all selected process parameters and the principal factor controlling the void crushing was identified as the reduction ratio.

원자력 발전소용 대형 튜브시트 단강품의 개발 (Development of the Large Tubesheet Forgings for Nuclear Power Plant)

  • 김동권;김영득;김동영
    • 한국소성가공학회:학술대회논문집
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    • 한국소성가공학회 2006년도 춘계학술대회 논문집
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    • pp.176-179
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    • 2006
  • Large tubesheet forgings of the steam generator for the 1,400MW nuclear power plant has been developed. Steam Generator is one of the most important structural part for nuclear power plant. It is manufactured by various steel forgings such as shell, head, torus and tubesheet. These steel forgings have been made by open die forging process. After steel melting and ingot making, open die forging has been carried out to get a good quality which means high soundness and homogeniety of the steel forgings by using high capacity hydraulic press. This paper introduced the forging process development and manufacturing experience of large tubesheet forgings which will be used for the steam generator of 1,400MW nuclear power plant.

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