• Title/Summary/Keyword: ASME A.17 series

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A Current State and an Implication of an Elevator Certification and Inspection System in U.S.A. (미국의 승강기 인증·검사체계의 현황과 시사점)

  • Kim, Young Jin
    • Journal of the Korean Society of Safety
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    • v.32 no.3
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    • pp.99-104
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    • 2017
  • An undeniable reason for elevator accidents is relevant to diverse defects of elevator itself including a fatal flaw in its managing system. In order to prevent and control disastrous accidents, Korean government established brand new department, Ministry of Public Safety and Security(MPSS) in 2014. For the field of elevator accidents, MPSS, hoping to take the lead, tries to reform related law and statutes. At this time, it is worthwhile to review foreign country's precedent to find out its applicable lesson. This study specially focuses on introducing U.S. legal system dealing with elevator safety area from the viewpoint of stressing the identity of local governments such as state, county, city etc. This article mainly reviews these four points: i) a current state of safety code, guide, standard for elevator in U.S.A. ii) an elevator parts certification system under ASME A.17.1, iii) an elevator inspection system in New York City, iv) an implication of an elevator certification and inspection system in U.S.A. to us.

Evaluation of the KN-12 Spent Fuel Transport Cask by Analysis

  • Chung, Sung-Hwan;Lee, Heung-Young;Song, Myung-Jae;Rudolf Diersch;Reiner Laug
    • Nuclear Engineering and Technology
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    • v.34 no.3
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    • pp.187-201
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    • 2002
  • The KN-12 cask is designed to transport 12 PWR spent nuclear fuels and to comply with the requirements of Korea Atomic Energy Act, IAEA Safety Standards Series No.57-1 and US 10 CFR Part 71 for a Type B(U)F package. It provides containment, radiation shielding, structural integrity, criticality control and heat removal for normal transport and hypothetical accident conditions. W.H 14$\times$14, 16$\times$16 and 17$\times$17 fuel assemblies with maximum allowable initial enrichment of 5.0 wt.%, maximum average burn-up of 50,000 MWD/MTU and minimum cooling time of 7 years being used in Korea will be loaded and subsequently transported under dry and wet conditions. A forged cylindrical cask body which constitutes the containment vessel is closed by a cask lid. Polyethylene rods for neutron shielding are arranged in two rows of longitudinal bore holes in the cask body wall. A fuel basket to accommodate up to 12 PWR fuel assemblies provides support of the fuels, control of criticality and a path to dissipate heat. Impact limiters to absorb the impact energy under the hypothetical accident conditions are attacked at the top and at the bottom side of the cask during transport. Handling weight loaded with water is 74.8 tons and transport weight loaded with water with the impact limiters is 84.3 tons. The cask will be licensed in accordance with Korea Atomic Energy Act 3nd fabricated in Korea in accordance with ASME B&PV Code Section 111, Division 3.