• Title/Summary/Keyword: Transport package

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Safety Evaluation of a Radioisotope Transport Package (방사성 동위원소 운반용기의 안전성 평가)

  • Lee, J.C.;Ku, J.H.;Seo, K.S.;Min, D.K.
    • Journal of Radiation Protection and Research
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    • v.22 no.4
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    • pp.251-261
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    • 1997
  • A package to transport the high level radioactive materials is required to withstand the hypothetical accident conditions as well as normal transport conditions according to IAEA standards and domestic regulations. The regulations require that the package should maintain the shielding, thermal and structural integrities to release no radioactive material. In general, safety evaluation of packages is performed by experimental methods using scale model and/or analytical methods using computer codes. This paper presents the safety evaluation of package to transport the radioisotopes produced in the HANARO to the radioisotope production facility. Radiation shielding, thermal and structural analyses were peformed using the computer codes. It has been verified that the package is safe under hypothetical accident conditions as well as normal transport conditions.

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A Preliminary Drop Test of a Type IP-2 Transport Package with a Bolted Lid Type (볼트체결방식의 IP-2형 운반용기의 낙하예비시험)

  • Kim Dong-Hak;Seo Ki-seog;Park Hong Yun;Lee Kyung Ho;Yoon Jeong-Hyoun;Lee Heung-Young
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11a
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    • pp.339-347
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    • 2005
  • A type IP-2 transport package should prevent a loss or dispersal of the radioactive contents and a more than $20\%$ increase in the maximum radiation level at any external surface of the package when it were subjected to the drop test under the normal conditions of transport. If a shielding thickness of IP-2 transport package is thick, a bolted lid type may prevent a loss or dispersal of the radioactive contents than the door type of ISO containers which are generally used as a type IP-2 transport package. In this paper, to evaluate the effect of drop directions on the bolt tension and the coherence of a bolt, the drop tests of preliminary small model are tested and evaluated for seven directions before the drop test of a type IP-2 transport package with a bolted lid type under the normal conditions of transport. Seven drop directions which are a bottom-vertical drop, a lid-vortical drop. a horizontal drop and four corner drops have been carried out. Using a force sensor, the bolt tension during the drop impact is measured. The coherence of bolt is evaluated by the difference between the fastening torque of bolt before a drop test and the unfastening torque of bolt after a drop impact.

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Structural Evaluation on the Impact of a Radioisotope Package

  • Chung, Sung-Hwan;Lee, Heung-Young;Ku, Jeong-Hoe;Seo, Ki-Seog;Han, Hyun-Soo
    • Nuclear Engineering and Technology
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    • v.30 no.5
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    • pp.462-469
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    • 1998
  • A package to transport high-level radioactive materials is required to withstand normal transport and hypothetical accident conditions pursuant to the IAEA and domestic regulations. The package should maintain the structural safety not to release radioactive material in any condition. The structural safety of the package has been evaluated by tests using proto-type or scaled-down models, however, the method by analysis is gradually utilized due to recent advancement of computers and computer codes. In this paper, to evaluate the structural safety of a radioisotope package of the KAERI, the three dimensional impact analyses under 9m free drop and 1m puncture were performed with an explicit finite-element code, the LS-DYNA3D code. The maximum stress intensity on each part was calculated and the structural safety of the package was evaluated in accordance with the regulations.

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Safety Evaluation of Radioactive Material Transport Package under Stacking Test Condition (방사성물질 운반용기의 적층시험조건에 대한 안전성 평가)

  • Lee, Ju-Chan;Seo, Ki-Seog;Yoo, Seong-Yeon
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.10 no.1
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    • pp.37-43
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    • 2012
  • Radioactive waste transport package was developed to transport eight drums of low and intermediate level waste(LILW) in accordance with the IAEA and domestic related regulations. The package is classified with industrial package IP-2. IP-2 package is required to undergo a free drop test and a stacking test. After free drop and stacking tests, it should prevent the loss or dispersal of radioactive contents, and loss of shielding integrity which would result in more than 20 % increase in the radiation level at any external surface of the package. The objective of this study is to establish the safety test method and procedure for stacking test and to prove the structural integrities of the IP-2 package. Stacking test and analysis were performed with a compressive load equal to five times the weight of the package for a period of 24 hours using a full scale model. Strains and displacements were measured at the corner fitting of the package during the stacking test. The measured strains and displacements were compared with the analysis results, and there were good agreements. It is very difficult to measure the deflection at the container base, so the maximum deflection of the container base was calculated by the analysis method. The maximum displacement at the corner fitting and deflection at the container base were less than their allowable values. Dimensions of the test model, thickness of shielding material and bolt torque were measured before and after the stacking test. Throughout the stacking test, it was found that there were no loss or dispersal of radioactive contents and no loss of shielding integrity. Thus, the package was shown to comply with the requirements to maintain structural integrity under the stacking condition.

Structural Safety Test and Analysis of Type IP-2 Transport Packages with Bolted Lid Type and Thick Steel Plate for Radioactive Waste Drums in a NPP (원자력발전소의 방사성폐기물 드럼 운반을 위한 볼트체결방식의 두꺼운 철판을 이용한 IP-2형 운반용기의 구조 안전성 해석 및 시험)

  • Lee, Sang-Jin;Kim, Dong-hak;Lee, Kyung-Ho;Kim, Jeong-Mook;Seo, Ki-Seog
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.5 no.3
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    • pp.199-212
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    • 2007
  • If a type IP-2 transport package were to be subjected to a free drop test and a penetration test under the normal conditions of transport, it should prevent a loss or dispersal of the radioactive contents and a more than 20% increase in the maximum radiation level at any external surface of the package. In this paper, we suggested the analytic method to evaluate the structural safety of a type IP-2 transport package using a thick steel plate for a structure part and a bolt for tying a bolt. Using an analysis a loss or dispersal of the radioactive contents and a loss of shielding integrity were confirmed for two kinds of type IP-2 transport packages to transport radioactive waste drums from a waste facility to a temporary storage site in a nuclear power plant. Under the free drop condition the maximum average stress at the bolts and the maximum opening displacement of a lid were compared with the tensile stress of a bolt and the steps in a lid, which were made to avoid a streaming radiation in the shielding path, to evaluate a loss or dispersal of radioactive waste contents. Also a loss of shielding integrity was evaluated using the maximum decrease in a shielding thickness. To verify the impact dynamic analysis for free drop test condition and evaluate experimentally the safety of two kinds of type IP-2 transport packages, free drop tests were conducted with various drop directions. For the tests we examined the failure of bolts and the deformation of flange to evaluate a loss or dispersal of radioactive material and measured the shielding thickness using a ultrasonic thickness gauge to assess a loss of shielding integrity. The strains and accelerations acquired from tests were compared with those by analyses to verify the impact dynamic analysis. The analytic results were larger than the those of test so that the analysis showed the conservative results. Finally, we evaluated the safety of the type IP-2 transport package under the stacking test condition using a finite element analysis. Under the stacking test condition, the maximum Tresca stress of the shielding material was 1/3 of the yielding stress. Two kinds of a type IP-2 transport package were safe for the free drop test condition and the stacking test condition.

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A Study on improving packaging design for Farm·Specialty purchase satisfaction (농·특산물 구매만족도 향상을 위한 포장디자인 개선에 관한 연구)

  • Park, Dong-Jin;Shin, Hwang-Ho;Woo, Soo-Gon
    • Journal of Korean Society of Rural Planning
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    • v.20 no.4
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    • pp.157-164
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    • 2014
  • This study clarified the correlation between the satisfaction of farm experience village visitors and the package design of farm specialty products and identified the factors to consider when improving the package design. It was found that the satisfaction with package design when purchasing farm specialty products affected the satisfaction of farm experience village visitors. In case of farm experience village visitors, they were more satisfied with the purchase when they were satisfied with the package design of farm specialty products they purchased. The results of analysis of correlation between the satisfaction of farm experience village visitors and the improvement of package design of farm specialty products showed that the important factors of package design are easiness of transport handling, easiness of storage, and functionality of packaging materials.

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.

Structural Analysis for the Container-Shaped Type A Package of Radioactive Materials (컨테이너형태의 방사성물질 A형 운반용기에 대한 구조해석)

  • 이영신;이호철;정성환;이흥영;김용재
    • Journal of the Computational Structural Engineering Institute of Korea
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    • v.14 no.2
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    • pp.143-150
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    • 2001
  • 원자력발전소의 1차 계통에서 오염된 장비들을 취급이 용이하고 안전하게 운반하기 위한 운반용기는 내부의 방사성 물질에 대한 방사능 평가에 의하여 방사성물질 A형 운반용기로 분류된다. 방사성물질 A형 운반용기는 IAEA Safety Standard Series No. ST-1 및 국내 원자력법 등 관련규정의 기술기준을 만족하여야 하는데, 운반용기는 중량에 따라 0.3∼1.2m의 높이에서 소성이 일어나지 않는 단단한 바닥면으로 가장 심각한 손상을 주는 방향으로 낙하시키는 정상운반조건(normal transport conditions)에 대하여 구조적 건전성을 유지하여야 한다. 여기서는 ABAQUS/Explicit 코드를 이용하여 컨테이너형태의 A형 운반용기에 대하여 최대손상이 야기되는 0.9m 경사낙하조건에 대한 3차원 충격해석을 수행하고 구조적 건전성을 평가하였는데, 운반용기는 경사낙하시 코너피팅(corner fitting)의 분쇄(crush)에 의하여 대부분의 충격을 흡수하였으며 운반용기의 격납경계는 구조적 건전성을 유지하였다.

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Development of an open-source GUI computer program for modelling irradiation of multi-segmented phantoms using grid-based system for PHITS

  • Hiroshi Watabe;Kwan Ngok Yu;Nursel Safakatti;Mehrdad Shahmohammadi Beni
    • Nuclear Engineering and Technology
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    • v.55 no.1
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    • pp.373-377
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    • 2023
  • The Monte Carlo (MC) method has become an indispensable part of the nuclear radiation research field. Several widely used and well-known MC packages were developed for simulation of radiation transport and interaction with matter. All these MC packages require users to prepare an input script. The input script can become lengthy for complex models. The process of preparing these input scripts is time-consuming and error-prone. In the present work, we have developed an open-source GUI computer program for modelling radiation transport and interaction in multi-segmented slab phantoms using grid-based system for the widely used PHITS MC package. The developed tools would be useful for future users of PHITS MC package and particularly inexperienced users. The present program is distributed under GPL license and all users can freely download, modify and redistribute the program without any restrictions.