KR200191370Y1 - Radiation shield block with paraffin plastic - Google Patents
Radiation shield block with paraffin plastic Download PDFInfo
- Publication number
- KR200191370Y1 KR200191370Y1 KR2019990030910U KR19990030910U KR200191370Y1 KR 200191370 Y1 KR200191370 Y1 KR 200191370Y1 KR 2019990030910 U KR2019990030910 U KR 2019990030910U KR 19990030910 U KR19990030910 U KR 19990030910U KR 200191370 Y1 KR200191370 Y1 KR 200191370Y1
- Authority
- KR
- South Korea
- Prior art keywords
- radiation
- shielding
- block
- paraffin
- shield
- Prior art date
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F3/00—Shielding characterised by its physical form, e.g. granules, or shape of the material
- G21F3/04—Bricks; Shields made up therefrom
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F1/00—Shielding characterised by the composition of the materials
- G21F1/02—Selection of uniform shielding materials
- G21F1/10—Organic substances; Dispersions in organic carriers
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Dispersion Chemistry (AREA)
- Compositions Of Macromolecular Compounds (AREA)
Abstract
본 고안은 방사선(중성자,감마,베타)차폐방법에 관한것으로 파라핀 플라스틱 재질로 구성된 블럭이 조립되어 방사선을 적절하게 차폐함을 목적으로 한다.The present invention relates to a method of shielding radiation (neutron, gamma, beta), and a block made of a paraffin plastic material is assembled for the purpose of adequately shielding radiation.
이를 위하여 차폐체가 좌블럭(1),중간블럭(2),우블럭(3)이 구성되고 방사선 발생 구역에 블럭을 상하좌우로 연결하였을때 방사선이 투과하지 못하도록 틈새가 없는 구조로 하였으며, 여러개를 쌓아 차폐벽이 형성될수 있도록 구성한다.For this purpose, the shield is composed of a left block (1), a middle block (2), and a right block (3), and has a structure without gaps so that radiation cannot penetrate when blocks are connected to the radiation generating area up, down, left and right. It is configured to be stacked to form a shielding wall.
통상적으로는 방사선 감마·베타 차폐용으로 납이 사용되고 있었으나 중성자 차폐를 효과적으로 할 수 있는 차폐체가 만들어지지 않아 복합적인 방사선 차폐에 방법이 적절하지 못하였다.Conventionally, lead was used for radiation gamma and beta shielding, but a shield was not made to effectively shield neutrons, so the method was not suitable for complex radiation shielding.
중성자 차폐에는 질량이 비슷한 수소(H), 산소(O), 탄소(C)등 가벼운 원자번호의 함유량이 많은 물질이 효과가 좋아 파라핀계열 플라스틱으로 차폐 블럭을 구성하여 중성자뿐만 아니라 감마·베타선 등 복합된 방사선을 차폐할 수 있어 방사선 차폐에 용이한 효과를 갖는다.For neutron shielding, a material with a high content of light atomic number such as hydrogen (H), oxygen (O), and carbon (C), which is similar in mass, is effective, forming a shielding block made of paraffin-based plastic, and combining neutrons with gamma and beta rays The shielded radiation can be shielded and has an easy effect on radiation shielding.
Description
본 고안은 원자력 발전소나 방사성동위원소 취급시설에서 방사선(중성자·감마·베타) 차폐에 관한 것으로 방사선 작업시 파라핀 플라스틱(Paraffin Plastic) 차폐 블럭을 설치하여 방사선을 차폐함으로써 원자력 분야 종사자의 피폭을 방지 할수있는 파라핀 플라스틱으로 구성한 방사선 차폐 블럭에 관한 것이다.The present invention relates to the shielding of radiation (neutrons, gamma, beta) in nuclear power plants or radioisotope handling facilities. A radiation shielding block composed of paraffin plastic.
종래에는 원자력 발전소나 방사성동위원소 취급시설에서 발생하는 방사선 차폐에 밀도가 큰 납을 재료로 한 차폐체를 사용하였으나 납은 무거워 운반의 어려움과 다양한 모형으로 제품화 할 수 없고 또한 방사선 중성자는 부딪치면 다시 튀어 나오는 반사(Albedo) 현상이 있어 원자력 발전설비 운영 중에 발생되는 중성자 차폐에는 효과가 적었고 통상 납 차폐체만 사용함으로써 원자력관련 종사자가 중성자에 의한 방사선 피폭에 문제점을 갖고 있었다.Conventionally, a shield made of dense lead material was used for radiation shielding in a nuclear power plant or radioisotope handling facility. Because of the reflection phenomenon, the neutron shielding generated during the operation of the nuclear power plant was less effective. Usually, only the lead shield was used, and nuclear workers had problems with radiation exposure by neutrons.
원자력 발전소나 방사성동위원소 취급설비 가동중 기기 조작 또는 보수 작업시 방사선(중성자·감마·베타) 발생에 의한 작업종사자의 외부피폭을 방지하기 위함이다.This is to prevent external exposure of workers by radiation (neutron, gamma, beta) generation during operation or repair of equipment while operating nuclear power plants or radioisotope handling facilities.
원자력분야 방사선 발생구역에 방사선차폐체로 납이 일부 사용되고 있으나 중성자 차폐에 효과가 좋은 파라핀 계열 플라스틱 차폐체 블럭이 없슴Although some lead is used as a radiation shield in the radiation area of the nuclear field, there is no paraffin-type plastic shield block that is effective for shielding neutrons.
본 고안의 과제는 방사선 중성자가 열중성자에서 속중성자에 이르기까지 각각 에너지 분포가 넓다(0.01eV∼1000Mev) 특히 중성자는 전하를 가지고 있지않고, 원자핵과의 탄성충돌에 의하여 에너지를 잃는다.The problem of the present invention is that the radiation neutrons have a wide energy distribution from thermal neutrons to fast neutrons (0.01 eV to 1000 Mev). Especially, neutrons do not have electric charges, and energy is lost by elastic collision with the atomic nucleus.
중성자가 차츰 에너지를 잃어 열중성자(0.025eV)가 되면 양성자와 전자로 붕괴된다. 따라서 중성자의 차폐체로는 원자번호가 가벼운 물질인 파라핀, 플라스틱이 적절하다.When neutrons gradually lose energy and become thermal neutrons (0.025 eV) they decay into protons and electrons. Therefore, as the shield of neutrons, paraffin and plastic, which have light atomic number, are suitable.
통상 기존 차폐체는 감마 베타선을 차폐하기 위한 목적으로 납이나 콘크리트 등을 사용하기 때문에 중성자 차폐에는 적절치 못한 문제점을 해결하고자 하는 것이다.Conventional shielding is to solve the problem that is not suitable for neutron shielding because it uses lead or concrete for the purpose of shielding gamma beta-rays.
제도는 본 고안의 사시도Drafting perspective view of the present invention
도면의 주요부호에 대한 설명Description of the main symbols in the drawings
1: 좌블럭1: left block
2: 중간블럭2: middle block
3: 우블럭3: right block
본 고안의 상기한 문제점을 해결하기 위해 수소(H), 산소(O), 탄소(C)등 가벼운 원자번호의 함유량이 많고 성형이 간편하며 가벼운 파라핀이 효과적이므로 파라핀 계열 플라스틱 재질로 차폐체 블럭이 되도록 구성한다.In order to solve the above problems of the present invention, since the content of light atomic number such as hydrogen (H), oxygen (O), carbon (C) is high, molding is easy and light paraffin is effective, the shielding block is made of paraffin-based plastic material. Configure.
본 고안은 방사선 중성자뿐만 아니라 감마·베타선에 의한 피폭 되는 것을 방지한 것으로 이를 첨부도면과 함께 설명하면 다음과 같다.The present invention prevents exposure to gamma and beta rays as well as radiation neutrons.
파라핀 플라스틱·사각형 블럭으로 좌블럭(1),중간블럭(2) 및 우블럭(3) 형태가 되는 구조로 했으며, 방사선 투과력과 범위에 적절하게 차폐할수있게 여러개를 상하좌우로 연결하여 사용할수 있는 형태로 고안했다.It is a paraffin plastic / square block that has the structure of left block (1), middle block (2) and right block (3), and it can be used by connecting several up, down, left and right to shield the radiation permeability and range properly. Devised in form
상기한 파라핀 플라스틱 방사선 차폐 블럭에 의해 원자력 발전소나 방사성동위원소 취급시설 운영중 발생하는 방사선으로 인한 작업종사자의 외부피폭을 방지 할 수 있고, 방사선 위해요소를 사전에 적절하게함으로써 원자력 분야 종사자를 방사선에 의해 피폭되는 문제점을 해소할수 있다.The above-mentioned paraffin plastic radiation shielding block can prevent external exposure of workers due to radiation generated during the operation of nuclear power plants or radioisotope handling facilities, and by appropriately setting radiation hazards in advance, The problem of exposure can be eliminated.
Claims (1)
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR2019990030910U KR200191370Y1 (en) | 1999-12-16 | 1999-12-16 | Radiation shield block with paraffin plastic |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
KR2019990030910U KR200191370Y1 (en) | 1999-12-16 | 1999-12-16 | Radiation shield block with paraffin plastic |
Publications (1)
Publication Number | Publication Date |
---|---|
KR200191370Y1 true KR200191370Y1 (en) | 2000-08-16 |
Family
ID=19605466
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
KR2019990030910U KR200191370Y1 (en) | 1999-12-16 | 1999-12-16 | Radiation shield block with paraffin plastic |
Country Status (1)
Country | Link |
---|---|
KR (1) | KR200191370Y1 (en) |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
WO2009151885A2 (en) * | 2008-05-19 | 2009-12-17 | Innovative American Technology Inc. | Modular radiation shield |
US8183538B2 (en) | 2001-10-26 | 2012-05-22 | Innovative American Technology Inc. | Sensor interface system |
US8247781B2 (en) | 2005-12-01 | 2012-08-21 | Innovative American Technology, Inc. | Fabrication of a high performance neutron detector with near zero gamma cross talk |
US8304740B1 (en) | 2008-05-19 | 2012-11-06 | Innovative American Technology, Inc. | Mobile frame structure with passive/active sensor arrays for non-invasive identification of hazardous materials |
US8330115B2 (en) | 2005-12-01 | 2012-12-11 | Innovative American Technology, Inc. | High performance neutron detector with near zero gamma cross talk |
KR20220091259A (en) | 2020-12-23 | 2022-06-30 | 계명대학교 산학협력단 | Radiation shielding fabric, its manufacturing method and radiation shielding articles using the same |
-
1999
- 1999-12-16 KR KR2019990030910U patent/KR200191370Y1/en not_active IP Right Cessation
Cited By (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US8183538B2 (en) | 2001-10-26 | 2012-05-22 | Innovative American Technology Inc. | Sensor interface system |
US8247781B2 (en) | 2005-12-01 | 2012-08-21 | Innovative American Technology, Inc. | Fabrication of a high performance neutron detector with near zero gamma cross talk |
US8330115B2 (en) | 2005-12-01 | 2012-12-11 | Innovative American Technology, Inc. | High performance neutron detector with near zero gamma cross talk |
US8466426B2 (en) | 2005-12-01 | 2013-06-18 | Innovative American Technology Inc. | Fabrication of a high performance neutron detector with near zero gamma cross talk |
WO2009151885A2 (en) * | 2008-05-19 | 2009-12-17 | Innovative American Technology Inc. | Modular radiation shield |
WO2009151885A3 (en) * | 2008-05-19 | 2010-03-11 | Innovative American Technology Inc. | Modular radiation shield |
US8304740B1 (en) | 2008-05-19 | 2012-11-06 | Innovative American Technology, Inc. | Mobile frame structure with passive/active sensor arrays for non-invasive identification of hazardous materials |
KR20220091259A (en) | 2020-12-23 | 2022-06-30 | 계명대학교 산학협력단 | Radiation shielding fabric, its manufacturing method and radiation shielding articles using the same |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US20060008044A1 (en) | Process and apparatus for the production of clean nuclear energy | |
KR200191370Y1 (en) | Radiation shield block with paraffin plastic | |
Krivopustov et al. | First experiments on transmutation studies of 129 I and 237 Np using relativistic protons of 3.7 GeV | |
JP2021021619A (en) | Metho for calculating air dose rate distribution | |
Huhtinen et al. | A Cross-comparison of MARS and FLUKA Simulation Codes | |
Tesch | Attenuation of the photon dose in labyrinths and ducts at accelerators | |
Pešic et al. | Comparison of the MCNP™ Calculated and Measured Radiation Field Quantities Near the RB Reactor | |
RU2461084C1 (en) | Nuclear reactor operating on quick neutrons | |
CN117790007A (en) | Sleeve type MA/UO in pressurized water reactor 2 Transmutation rod | |
Ma et al. | The study on spatial homogenization parameters based upon equivalence theory | |
Kochnov et al. | Effects of various types of reflectors on the 99Mo production in the VVER-Ts reactor targets | |
ES296030U (en) | Antiradiation shield for nuclear reactors, as well as the parts thereof and a method for producing them | |
KR200333559Y1 (en) | Radiation shielding brick | |
Takahashi et al. | Accelerator breeder with uranium, thorium target | |
Taylor | Neutronics study of a spherical tokamak for component testing | |
Farrar IV et al. | SILENE, a new radiation reference source | |
Szöllős et al. | THE USE OF THE PHOTOFISSION OF 238U FOR A NEUTRON–RICH RADIOACTIVE ION BEAMS GENERATION | |
Job et al. | Dose rate estimates in the first optical enclosure due to particle beam loss in the insertion device transition region during injection | |
Ben-Shachar et al. | Some dosimetric properties of the LiF: Mg, Ti evaluated by the automatic 6600 thermoluminescent reader | |
Stavissky | Spallation neutron sources at the INR RAS: present status and prospects | |
Orion et al. | Locating gamma radiation source by self collimating BGO detector system | |
SE1851249A1 (en) | A method for converting nuclear energy into thermal energy and a device for implementing the method (embodiments) | |
Gerasimov et al. | Cyclic mode of transmutation of minor actinides in heavy-water reactor | |
Belogorlov et al. | Neutron spectra at the outlet from the labyrinths in the IHEP proton synchrotron biological shield | |
Zaitsev et al. | Polymerconcrete for Radiation Background Shielding of Detectors at Hadron Colliders |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
REGI | Registration of establishment | ||
N231 | Notification of change of applicant | ||
FPAY | Annual fee payment |
Payment date: 20040521 Year of fee payment: 5 |
|
LAPS | Lapse due to unpaid annual fee |