• Title/Summary/Keyword: Transport Cask

Search Result 64, Processing Time 0.084 seconds

A Study on the Nuclear Transport Cask under Projectile Impact (원자력 운반용기의 탄자충격에 대한 연구)

  • Kim, Jeong-Hyun;Lee, Young-Shin;Lee, Hyun-Seung;Chung, Sung-Hwan
    • Proceedings of the Computational Structural Engineering Institute Conference
    • /
    • 2011.04a
    • /
    • pp.735-738
    • /
    • 2011
  • 본 논문에서는 LS-DYNA를 이용하여 원자력 운반용기의 탄자충격에 대한 해석을 수행하였다. 문명의 발달과 더불어 원자력 발전소는 많이 생겼으며 미래에도 유망하다. 원자력 발전소에서 발생되는 사용 후 핵연료에는 환경이나 사람들에게 유해한 방사성 물질이 포함되어 있기 때문에 이를 운반하는 운반용기에 대한 구조적 안전성 확보가 필요하다. 운반용기의 이동과정에서 여러 가지 사고가 날 수 있으므로 이에 대한 대비가 필요하다. 해석에는 운반플라스크와 컨테이너가 사용되었다. 운반플라스크 안에 컨테이너가 들어가 있는 형상을 갖는데 이 부분에 탄자 충격을 가하고, 이 때 운반용기에서 받는 충격량과 변화에 대해 관찰하였다. 탄자도 실제 상황과 비슷하게 하기 위해 보편적으로 사용되는 k-2 소총에 들어가는 것으로 사용하였다. 이를 통하여 운반용기에 탄자충격이 가해졌을 때 구조적 안전성을 평가하였다.

  • PDF

Rotational position control of RCGLUD using input shaping algorithm (입력 다듬기를 이용한 사용후 핵연료 수송용기 취급장치의 회전 위치제어)

  • 김동기;박영수;윤지섭
    • 제어로봇시스템학회:학술대회논문집
    • /
    • 1996.10b
    • /
    • pp.1060-1063
    • /
    • 1996
  • Remote Cask Grappling and Lid Unbolting Device (RCGLUD) is developed as a dedicated device capable of performing complete procedure of handling nuclear spent fuel transport cask. Since RCGLUD is suspended to an overhead crane, its body should undergo prolonged vibration upon actuation in rotational direction and it becomes difficult to achieve precise grappling of the cask. Therefore, this paper presents an adaptation of input shaping technique to effectively suppress the rotational vibration of RCGLUD and achieve precise positioning in rotational direction. This technique has a practical merit in that it requires only the information on the system natural frequency and the damping ratio. Its performance is verified by both simulation and experimental studies, and revealed that the method is also insensitive to modeling error.

  • PDF

Analysis Method on the Free Drop Impact Condition of Spent Nuclear Fuel Shipping Casks (자유낙하충격조건에 있는 사용후핵연료 운반용기의 충격해석방법 연구)

  • 이재형;이영신;류충현;나재연
    • Proceedings of the Korean Society for Noise and Vibration Engineering Conference
    • /
    • 2001.11b
    • /
    • pp.766-771
    • /
    • 2001
  • The package used to transport radioactive materials, which is called by cask, must be safe under normal and hypothetical accident conditions. These requirements for the cask design must be verified through test or finite element analysis. Since the cost for FE analysis is less than one for test. the verification by FE analysis is mainly used. But due to the complexity of mechanical behaviors. the results depends on how users apply the codes and it can cause severe errors during analysis. In this paper, finite element analysis is carried out for the 9 meters free drop and the puncture condition of the hypothetical accident conditions using LS-DYNA3D and ABAQUS/Explicit. We have investigated the analyzing technique for the free drop impact test of the cask and found several vulnerable cases to errors. The analyzed results were compared with each other. We have suggested a reliable and relatively simple analysis technique for the drop test of spent nuclear fuel casks.

  • PDF

A mite Element Modeling for the Puncture Drop Test of a Cask with the Failure of Impact Limiter (충격완충체의 효과를 고려할 수 있는 운반용기의 파열낙하시험 유한요소해석 방법)

  • Kwon, Kie-Chan;Seo, Ki-Seog;You, Gil-Sung
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.7 no.1
    • /
    • pp.9-16
    • /
    • 2009
  • Transport package for radioactive material should be structurally safe under puncture drop condition and its safety should be verified by test and numerical analysis. Most finite element analyses for puncture drop have been performed without modeling the impact limiter since failure is occurred in the materials of the impact limiter. This paper presents a new modeling methodology, where an element is eroded in case that the material's failure criteria are reached at the element's integration point, to investigate the effect of the impact limiter in the puncture process. The effectiveness of the proposed scheme is shown through the puncture drop analysis of hotcell transport cask, which is under design in KAERI. The results show that about 80 percent of the total impact energy is absorbed due to the deformation of impact limiter. Using the present method the puncture drop can be analyzed more accurately, but it would give conservative results compared to the actual test condition.

  • PDF