• Title/Summary/Keyword: 차폐 콘크리트

Search Result 115, Processing Time 0.027 seconds

A Study on the Construction of High Density Concrete for Radiation Shield (방사선 차폐용 고밀도 콘크리트 시공에 관한 연구)

  • 이제방;조용복;변형균;유건철;임병대
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 1994.10a
    • /
    • pp.399-404
    • /
    • 1994
  • Heavyweight(or High density) concrete, which is generally for shiedling structures, differs from normal weight concrete by having a higher density and special compositions to improve its attenuation properties. There are setting 7 Beam Ports around the reactor of the KMRR Project(Korea Multi-purpose Research Reactor) conducted by the KAERI(Korea Atomic Energy Research Institute). High density(p=5.0t/$\textrm{m}^3$) and Heavyweight(p=3.5t/$\textrm{m}^3$) concrete were placed around the Beam Ports in order to shield radiation. This paper was discussed about construction of High density concrete. High density concrete was placed with method of Preplace Aggregate. Coarse metallic aggregate(steel shot) was used. Boron, boron carbide(B4C), was used to capture effctively the neutrom. The mock-up test was carried out. And the consturction of High density concrete was performed successfully.

  • PDF

A Study on the Shielding Analysis in Vitrification Facility of Low-and Intermediate Level Radioactive Wastes ($\cdot$저준위 방사성폐기물 유리화 시설의 차폐해석에 관한 연구)

  • 이창민;이건재;지평국;박종길;하종현;송명재
    • Proceedings of the Korean Radioactive Waste Society Conference
    • /
    • 2003.11a
    • /
    • pp.524-531
    • /
    • 2003
  • The usefulness of vitrification technology for low- and intermediate- level radioactive wastes was demonstrated because of high volume reduction, mechanical and chemical stability of final waste forms. Thus, a construction of the commercial vitrification plant Is currently promoted. Due to the high radiation level of the waste, shielding analysis has to be carried out for safe design in a vitrification facility. Because there has been no experience in the construction and operation of the vitrification facility in Korea, in this study, in order to get some information for help the detailed design and plan for operation in vitrification facility, shielding analysis for each facility in pilot plant is carried out by using source term from established study. For the selection of the shielding material, concrete was chosen compared to the lead because of economic advantage, weight consideration, and thermal resistance.

  • PDF

Evaluate the Activation of Linear Accelerator Components and Shielding Wall through Simulation (모의실험을 통한 선형가속기 부품과 차폐벽의 방사화 평가)

  • Lee, Dong-Yeon;Park, Eun-Tae;Kim, Jung-Hoon
    • The Journal of the Korea Contents Association
    • /
    • v.17 no.9
    • /
    • pp.69-76
    • /
    • 2017
  • This study evaluated the activation of the shielding wall and the components around the accelerator by using the medical linear accelerator. We performed simulations for energy values of 20 MV with the operating time ranging from day 1 to 30 years, and linear accelerator head and shielding wall concrete were also evaluated. The results showed that neutrons in large quantities were analyzed using high energy around thetarget point where photons were formed. Based on the activation analysis with these results, radioactivity increased with an increase in operation time and activated nuclides usually start saturating in10 years. Furthermore, the general types of nuclides formed owingto the activation were Co-60, W-181, 185, 187, Na-24, Ca-45, Mn-54, 56, and Fe-55, 59.

Development of the Pushing Type Cutting Device to Dismantle Concrete Structure for Decommissioning of Nuclear Power Plant (원전해체 시 콘크리트 구조물 절단을 위한 밀기형 절단장치 개발)

  • Lee, Bong-Jae;Kwon, Yong-Kyu;Hong, Chang-Dong;Lee, Dong-Won;Min, Kyong-Nam
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
    • /
    • v.18 no.1
    • /
    • pp.103-111
    • /
    • 2020
  • Pulling-type cutting devices, which use a diamond wire saw, have been used generally for cutting concrete structures. In this study, a pushing-type cutting device with a collection cover was developed by overcoming the disadvantages of pulling-type devices. In this device, dry or liquid methods can be selected to cool frictional heat. Operation and leakage tests of the dust generated during the dismantling of a concrete structure were carried out, confirming the suitable operation of the fabricated cutting device; the leakage rate was approximately 1.7%. For a conservative evaluation, the internal dose of workers was estimated in dismantling the core center part of biological shield concrete with a specific activity of 99.5 Bq·g-1. The committed effective dose per worker was 0.25 mSv. The developed cutting device contributed to reducing radioactive concrete waste and minimizing worker exposure due to its easy installation. Therefore, it can be utilized as a cutting apparatus for dismantling not only reinforced concrete structures but also radioactive biological shield concrete in nuclear power plant decommissioning efforts.

사용후핵연료 중간저장(건식형태)시설의 구조 및 설비기준 개발

  • 김영상;이상국
    • Proceedings of the Korean Nuclear Society Conference
    • /
    • 1996.05d
    • /
    • pp.247-252
    • /
    • 1996
  • 사용후핵연료 건식 중간저장시설은 설계수명기간 동안 방사능 차폐, 냉각, 보호 등과 같은 주요 기능이 확실히 보장되도록 설계 및 유지·관리되어야 한다. 이러한 주요 기능은 여러가지 설계하중 하에서 구조물의 거동을 정확히 파악한 결과를 설계에 반영함으로써 보장된다. 본 연구에서는 구조물의 건전성을 보장할 수 있는 기능적 측면과 구조적 측면에서 고려되어야 할 항목 및 내용을 국외에서 적용되고 있는 기술기준을 토대로 하고 풍하중, 홍수방호, 내진설계, 열하중해석, 철근콘크리트 및 강구조물, 기초지반과 같은 세부항목에 대한 해석 및 설계의 연구결과를 추가하여 국내 원자력법령과 시행령에 부합되는 사용후핵연료 건식중간저장시설의 구조 및 설비기준을 개발하였다.

  • PDF

Development of Risk Breakdown Structure of Nuclear Power Plant Decommissioning Project: Focusing on Structural Damage / Work Process Risks (원전 차폐 콘크리트 구조물 제염해체공사 리스크 분류체계 구축: 구조적 / 작업 리스크를 중심으로)

  • Kim, Byeol;Lee, Joo-Sung;Ahn, Yong-Han
    • Journal of the Korea institute for structural maintenance and inspection
    • /
    • v.22 no.3
    • /
    • pp.38-45
    • /
    • 2018
  • The purpose of this study is to deduct the structural damage / work process risks factors which can be occurred during the decommissioning in the NPP containment concrete structure. To achieve these purpose, risk profile specified in the construction industry is analyzed, and the work process of NPP decommissioning and the construction project were matched based on the similarity of each works. Accordingly, human and physical risk factors are classified. Finally, the risk associated with the building structure and work process was classified as per their process activities, and risk typology explaining the disaster which put the structure, equipments, machine and workers in serious danger was developed.

Hydraulic Experiment on Roughness Coefficient of PE pipe (폴리에틸렌관의 조도계수에 관한 수리모형실험)

  • Dongwoo Ko;Byeong Wook Lee;Jae-Seon Yoon;Hyun-Gu Song
    • Proceedings of the Korea Water Resources Association Conference
    • /
    • 2023.05a
    • /
    • pp.288-288
    • /
    • 2023
  • 도로, 철도 등의 횡단통로, 오폐수관로, 지하배수관 등 연약지반에서 상재하중과 부등침하에 의한 파괴 위험을 줄이기 위해 구조적인 안전성과 내구성이 개선된 다양한 관로들이 활용되고 있다. 관은 매설특성에 따라 콘크리트관, 도관, 합성수지관, 덕타일 주철관, 파형강관, 유리섬유 강화 플라스틱과 폴리에스테르수지 콘크리트관 등의 종류로 구분된다(환경부, 2017). 수리설계 시 이러한 관의 단면 규모 결정 및 흐름 특성을 파악하기 위해 관수로 유량측정에 이용되는 Manning의 경험식을 이용하고 있으며, 관로의 주요 재질에 따른 다양한 조도계수가 제시되어 있다. 새로운 재질을 이용하여 제작된 관은 수리실험을 통해 조도계수를 결정하는 것이 바람직하지만, 조도계수 실험은 대규모의 실험시설과 유량공급이 요구되기 때문에 여러 한계가 있다. PE관의 경우, 미국의 ASTM 표준에 의해 저밀도 폴리에틸렌(LDPE), 선형 저밀도 폴리에틸렌(LLDPE), 고밀도 폴리에틸렌(HDPE) 등으로 분류되는데 본 연구에서는 HDPE 재질의 서로 직경이 다른 다중벽관 PE관을 대상으로 조도계수를 결정하기 위한 현장 실규모 수리실험을 수행하였다. 본 실험에서는 식생, 수로의 불규칙성, 수로노선, 침전과 세굴, 장애물, 계절적 변화, 부유물질과 소류사는 무시되며 표면조도, 관의 크기와 형상, 수위와 유량이 조도계수에 영향을 미치는 주요 인자라고 할 수 있다. 수리실험은 실물모형(Prototype)으로 한국농어촌공사 농어촌연구원의 대형수리모형실험장에서 수행되었으며. 길이 24 m, 직경 150 mm의 PE 관은 고정식 개수로, 직경 800 mm의 관은 대형유사순환수로에 각각 설치되었다. 관로의 전면에 차폐막을 설치하여 상류부 수위를 안정시킨 상태에서 실험을 수행하였고, 차폐막으로부터 하류방향으로 약 7 m(측정기준지점), 11 m, 13 m, 15 m, 17 m 떨어진 곳에서 각각 수위와 유속을 측정하였다. 실험 결과, φ150관은 직경대비 수심이 클수록 조도계수가 감소하는 경향이 나타났고, φ800관은 직경대비 수심의 변화에 따른 조도계수의 경향이 크게 드러나지 않았다. 결론적으로 PE관의 조도계수는 수심별로 변화하는 것으로 나타났으며, 특정 수심을 지나면 조도계수가 다시 감소할 것으로 판단된다.

  • PDF

A Study on the Radiation Shielding Analysis for Reinforcing the Hot Cell Regular Concrete Shield Wall (핫셀의 일반 콘크리트 보강을 위한 방사선 차폐해석 연구)

  • 조일제;황용화
    • Proceedings of the Korea Concrete Institute Conference
    • /
    • 2003.05a
    • /
    • pp.985-990
    • /
    • 2003
  • In order to demonstrate Advanced Spent Fuel Conditioning Process (ACP), shielding facilities such as hot cell suitable to handling radionuclides and process property will be necessary. But the construction of new facilities needs much money, man-power and time, it is now scheduled to remodel the hot cell, which has already been installed and maintained at Irradiated Material Experiment Facility (IMEF) in the Korea Atomic Energy Research Institute (KAERI). The basic structure and concrete shield wall of hot cell partly have been constructed on the base floor in IMEF building in current status. And hot cell after remodeling will be used for carrying out the lab-scale experiment of ACP. The hot cell was built in accordance with 35 curies of fe-59(1.2 MeV) as design criteria of radiation dose limit. But the radioactive source of ACP is expected to be much higher than design criteria of IMEF, shielding ability of the hot cell in the current status is unsatisfactory to the hot test of ACP. Therefore shield wall shall be reinforced with heavy concrete, steel or lead. In this paper, dose rates are calculated according to ACP source, shielding materials, etc., and reinforcement structures are determined considering the current situation of hot cells, installation of shield windows and the easiness of work.

  • PDF

Evaluation on High Altitude Electromagnetic Pulse(HEMP) Protection Performance of Carbon Nanotube(CNT) Embedded Ultra-High Performance Concrete(UHPC) (탄소나노튜브(CNT)를 혼입한 초고성능 콘크리트(UHPC)의 고고도 전자기파(HEMP) 방호성능 평가)

  • Jung, Myungjun;Hong, Sung-gul
    • Journal of the Korea Institute of Military Science and Technology
    • /
    • v.22 no.2
    • /
    • pp.151-161
    • /
    • 2019
  • In this study, to evaluate the High Altitude Electromagnetic Pulse(HEMP) protection performance of UHPC/CNT composites by the content of Carbon nanotubes(CNTs), Electromagnetic Shielding Effectiveness(SE) test was performed based on MIL-STD-188-125-1. And the results were verified by applying the Antenna theory. In the case of UHPC with a thickness of 200 mm mixed with 1 % CNT of cement weight, the SE was 28.98 dB at 10 kHz and 45.94 dB at 1 GHz. Then the Scabbing limit thickness for bullet proof was computed based on the result of compressive strength test which was 170 MPa, and it was examined whether it satisfied the HEMP protection criteria. As a result, the required HEMP shielding criteria were satisfied in all frequency ranges as well as the scabbing limit thickness was reduced by up to 43 % compared with that of ordinary concrete.

Generation of Gamma-Ray Streaming Kernels Through Cylindrical Ducts Via Monte Carlo Method (몬테칼로 방법을 이용한 원통형 관통부의 감마선 스트리밍 커널의 산출)

  • Kim, Dong-Su;Cho, Nam-Zin
    • Nuclear Engineering and Technology
    • /
    • v.25 no.1
    • /
    • pp.80-90
    • /
    • 1993
  • Radiation streaming through penetrations has been of great concern in radiation shielding design and analysis. This study developed a Monte Carlo method and constructed a data library of results calculated by the Monte Carlo method for radiation streaming through a straight cylindrical duct in concrete walls of a broad, mono-directional, mono-energetic gamma-ray beam of unit intensity. It was demonstrated that average dose rate due to an isotropic point source at arbitrary positions can be well approximated using the library with acceptable error. Thus, the library can be used for efficient analysis of radiation streaming due to arbitrary distributions of gamma-ray sources.

  • PDF