Radiation Protection and Safety in Industrial Radiography
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Radiation Risk in Perspective
PS010-1 RADIATION RISK IN PERSPECTIVE POSITION STATEMENT OF THE HEALTH HEALTH PHYSICS SOCIETY* PHYSICS SOCIETY Adopted: January 1996 Revised: August 2004 Contact: Richard J. Burk, Jr. Executive Secretary Health Physics Society Telephone: 703-790-1745 Fax: 703-790-2672 Email: [email protected] http://www.hps.org In accordance with current knowledge of radiation health risks, the Health Physics Society recommends against quantitative estimation of health risks below an individual dose of 5 rem1 in one year or a lifetime dose of 10 rem above that received from natural sources. Doses from natural background radiation in the United States average about 0.3 rem per year. A dose of 5 rem will be accumulated in the first 17 years of life and about 25 rem in a lifetime of 80 years. Estimation of health risk associated with radiation doses that are of similar magnitude as those received from natural sources should be strictly qualitative and encompass a range of hypothetical health outcomes, including the possibility of no adverse health effects at such low levels. There is substantial and convincing scientific evidence for health risks following high-dose exposures. However, below 5–10 rem (which includes occupational and environmental exposures), risks of health effects are either too small to be observed or are nonexistent. In part because of the insurmountable intrinsic and methodological difficulties in determining if the health effects that are demonstrated at high radiation doses are also present at low doses, current radiation protection standards and practices are based on the premise that any radiation dose, no matter how small, may result in detrimental health effects, such as cancer and hereditary genetic damage. -
Assessment of Occupational Radiation Exposure from Industrial Radiography Practice
Transactions of the Korean Nuclear Society Virtual spring Meeting May 13 -14, 2021 Assessment of Occupational Radiation Exposure from Industrial Radiography Practice Soja Reuben Joseph and Juyoul Kim* Department of NPP Engineering, KEPCO International Nuclear Graduate School, 658-91 Haemaji-ro, Seosaeng-myeon, Ulju-gun, Ulsan 45014 *Corresponding author: [email protected] 1. Introduction used for industrial gamma radiography applications to inspect materials and structures in the density range of Reports of high radiation-related accidents have been approximately 2.71 g/cm3 through 8.53 g/cm3. The linked with industrial radiography than any other exposure device body is shielded with depleted uranium radiography sub-specialty, mainly due to deviation from (DU) or Tungsten (W) shield is encased within a welded standard operating procedures (SOP) and radiation tubular stainless-steel shell end plates, aluminum, brass, protection practices resulting to workers exposure [1]. tungsten and polyurethane with labels, comprises details Industrial gamma radiography is one of the most of radioactive material and transportation package type commonly used non-destructive testing (NDT) methods among others as shown in Fig. 1 [6]. The authorized that employs a technique of inspecting materials for contents of Sentinel model 880 series source projectors hidden flaws by using high activity sealed radioactive parameters are shown in Table I. source housed in a shielded exposure device (commonly known as source projectors) for used in imaging of weld joints and castings and must be managed safely and securely [2]. The devices are operated manually by spinning the controller unit to project the gamma source outside the shielding, in a projection casing. -
Radiation Shielding Design Assessment and Verification Requirements 17
4. High-risk premises 4.1 General description 4.1.1 Premises are classified as high-risk where the potential for radiation exposure is high and substantial shielding is required to operate within dose limits. 4.1.2 A shielding plan must be prepared for all high-risk premises as detailed in Section 6 of this guideline. Complex shielding plans for high risk premises may require significantly more detail than the minimum requirements listed in Section 6. 4.1.3 There is no requirement that the shielding plan be prepared by a CRE, however, the plan must be assessed by an appropriately accredited CRE to ensure compliance with this guideline. In addition, for all premises classified as high risk, a second CRE who is appropriately accredited must carry out an independent assessment of the shielding plan to verify that the plan is satisfactory for the proposed use and that it is compliant with the requirements of this guideline. The shielding plan must be certified by the second CRE. 4.2 High-risk applications 4.2.1 Premises not classified as low or medium are considered to be high risk. These include: a. radiotherapy using a sealed source or irradiating apparatus greater than 150 kVp, including remote after-loading devices b. positron emission tomography (PET) c. in patient isolation facility for nuclear medicine therapy using unsealed gamma emitting radionuclides d. industrial radiography in fully-or partially-enclosed sites and other industrial, research and non-medical activities using radiation apparatus or using and storing sealed sources (where the activity thresholds for sealed radioactive sources, or aggregation of, are categorised as category 1, 2 or 3 as listed in Appendix A,). -
Non-Medical Industrial Radiography V2
Minnesota Rules, Chapter 4732 X-Ray Revision DRAFT INDUSTRIAL RADIOGRAPHY X-RAY SYSTEMS, 2.0 (03/09/2018) Summary of Changes MDH made a number of changes to the Industrial Radiography rule draft v1.0 based on the industrial focus group’s review and feedback at the March 1, 2018 meeting. Substantive changes to version 1.0 are described below. Subp. 2. Safety device. • Deleted item C Subp. 3. Warning lights and devices. • Revised wording in item B Subp. 5. Shutters. • Deleted “either” and “or a coupling” in item A. • Deleted item B Subp. 7. Safety device evaluation. • Item C (2). inserted “if applicable” Subp. 8. Radiation emission limit. • Deleted this subpart. Subp. 8. Radiation protection survey. (formerly Subp. 10) • Renumbered • Revised first sentence inserting underscored language: A registrant is responsible for performing a radiation protection survey for a permanent installation of an industrial radiography x-ray system that includes all beam directions. • Item A. Deleted “of an industrial radiography x-ray system in a permanent location” Subp. 9. Area survey. (formerly Subp. 11) • Renumbered; no changes Subp. 10. Radiation safety officer; qualifications. (formerly Subp. 12) • Renumbered • Updated internal reference in item A. DRAFT INDUSTRIAL RADIOGRAPHY X - RAY SYSTEMS, 2.0 (03/09/2018) • Revised item B by inserting “to include 40 hours of classroom training in the establishment and maintenance of a radiation safety protection program” • Deleted item C Subp. 11. Alternate qualifications. (formerly Subp. 13) • Renumbered; no changes Subp. 12. Radiation safety officer; authority and duties. (formerly Subp. 14) • Renumbered; no changes Subp. 13. Radiographer requirements. (formerly Subp. -
Radiographic Sensitivity in Industrial Radiographic Testing with X-Ray Films
Malaysia International NDT Conference & Exhibition 2015 (MINDTCE-15), Nov 22-24 - www.ndt.net/app.MINDTCE-15 Radiographic Sensitivity in Industrial Radiographic Testing With X-Ray Films By: Tee Kim-Tsew (Technical Manager, Lott Inspection Sdn. Bhd., Malaysia ASNT and ACCP Level III) Abstract. Radiographic Testing (RT) is widely used in industries, at airport for security checks, medical More Info at Open Access Database www.ndt.net/?id=18665 applications etc. to detect anomalies in materials and human bodies. Radiographic Testing is the common NDT methods used in the construction and fabrication industries for the oil & gas sectors using welding, gas/liquid transmission pipelines, casting foundries, and condition monitoring in existing oil & gas refineries and facilities. This paper will discuss radiographic testing sensitivity using industrial X-ray films mainly on welds and castings. No in-depth discussion in related science and physics, merely the perspective of an industrial radiographer based on his experience. Keywords: IQI, Quantitative, Qualitative, sensitivity, contrast, definition, geometric un-sharpness INTRODUCTION The basic principle for the detection of anomalies using radiographic testing method is the difference in radiation absorption coefficients properties exhibits by different materials. The images are captured in a recording medium. The recording medium used may be X-ray film, phosphorous imaging plates, diodes etc. Industrial X-ray films are the common recording medium used for these applications. RADIOGRAPHIC TESTING SENSITIVITY Like all other NDT methods, certain detection sensitivity is required for the technique to ensure detectability of desired anomalies. In industrial radiography, Radiographic Sensitivity is a QUALITATIVE term referring to the size of the smallest detail that can be recorded and discernible on the film/radiograph, or to the ease with which the images of small details can be recorded. -
Industrial Radiography
RADIATION PROTECTION OF WORKERS Industrial Radiography RADIATION AND RADIOGRAPHS RADIOACTIVE SOURCES PROCEDURES RADIOGRAPHERS DO follow the procedures. Ionizing radiation can pen- Materials of higher den Sealed sources are small þ Safe storage Precautions þ DO use the appropriate equipment, including collimators. in size and contain material etrate objects and create sity absorb more radiation. þ DO confi rm that there are no other people working in the images on photographic The metal components are which emits penetrating area of radiography. fi lm. The technique is revealed inside this tele radiation continuously. Radioactive sources should be kept in a secure, fi re þ DO use clear working signs and signals. called radiography and phone because they have Special containers made þ DO set up the controlled area and the necessary barriers. the processed fi lms are absorbed more radiation of dense metal shielding resistant and adequately shielded storage location þ DO confi rm the location of the source, or that X rays are called radiographs. than the surrounding plastic. are necessary to store, not being generated, by use of a survey meter. when not in use, and should move and manipulate these þ DO secure and store the source or X ray machine when sources. Due to their small be kept separate from other not in use. materials. The storage loca- size and manoeuvrability, Portable and mobile radiographic þ DO wear your personal dosimeter. sealed sources can be containers. ~ tion for X ray machines that used in confined spaces. are not in use is not required to be shielded. OTHER WORKERS Iridium-192 is a common radioactive source used þ DO observe the access restrictions, however remote it may in gamma radiography. -
Lessons Learned from Accidents in Industrial
VIC Library JffiW Safety Reports Series No. 7 LESSONS LEARNED FROM ACCIDENTS IN INDUSTRIAL RADIOGRAPHY The following States are Members of the International Atomic Energy Agency: AFGHANISTAN HOLY SEE PARAGUAY ALBANIA HUNGARY PERU ALGERIA ICELAND PHILIPPINES ARGENTINA INDIA POLAND ARMENIA INDONESIA PORTUGAL AUSTRALIA IRAN, ISLAMIC REPUBLIC OF QATAR AUSTRIA IRAQ REPUBLIC OF MOLDOVA BANGLADESH IRELAND ROMANIA BELARUS ISRAEL RUSSIAN FEDERATION BELGIUM ITALY SAUDI ARABIA BOLIVIA JAMAICA SENEGAL BOSNIA AND JAPAN SIERRA LEONE HERZEGOVINA JORDAN SINGAPORE BRAZIL KAZAKHSTAN SLOVAKIA BULGARIA KENYA SLOVENIA CAMBODIA KOREA, REPUBLIC OF SOUTH AFRICA CAMEROON KUWAIT SPAIN CANADA LATVIA SRI LANKA CHILE LEBANON SUDAN CHINA LIBERIA SWEDEN COLOMBIA LIBYAN ARAB JAMAHIRIYA SWITZERLAND COSTA RICA LIECHTENSTEIN SYRIAN ARAB REPUBLIC COTE D’IVOIRE LITHUANIA THAILAND CROATIA LUXEMBOURG THE FORMER YUGOSLAV CUBA MADAGASCAR REPUBLIC OF MACEDONIA CYPRUS MALAYSIA TUNISIA CZECH REPUBLIC MALI TURKEY DEMOCRATIC REPUBLIC MALTA UGANDA OF THE CONGO MARSHALL ISLANDS UKRAINE DENMARK MAURITIUS UNITED ARAB EMIRATES DOMINICAN REPUBLIC MEXICO UNITED KINGDOM OF ECUADOR MONACO GREAT BRITAIN AND EGYPT MONGOLIA NORTHERN IRELAND EL SALVADOR MOROCCO UNITED REPUBLIC ESTONIA MYANMAR OF TANZANIA ETHIOPIA NAMIBIA UNITED STATES FINLAND NETHERLANDS OF AMERICA FRANCE NEW ZEALAND URUGUAY GABON NICARAGUA UZBEKISTAN GEORGIA NIGER VENEZUELA GERMANY NIGERIA VIET NAM GHANA NORWAY YEMEN GREECE PAKISTAN YUGOSLAVIA GUATEMALA PANAMA ZAMBIA HAITI ZIMBABWE The Agency’s Statute was approved on 23 October 1956 by the Conference on the Statute of the IAEA held at United Nations Headquarters, New York; it entered into force on 29 July 1957. The Headquarters of the Agency are situated in Vienna. Its principal objective is “to accelerate and enlarge the contribution of atomic energy to peace, health and prosperity throughout the world” . -
Occupational Radiation Protection Record-Keeping and Reporting Guide
DOE G 441.1-11 (formerly G-10 CFR 835/H1) 05-20-99 OCCUPATIONAL RADIATION PROTECTION RECORD-KEEPING AND REPORTING GUIDE for use with Title 10, Code of Federal Regulations, Part 835, Occupational Radiation Protection Assistant Secretary for Environment, Safety and Health (THIS PAGE INTENTIONALLY LEFT BLANK) DOE G 441.1-11 i 05-20-99 CONTENTS CONTENTS PAGE 1. PURPOSE AND APPLICABILITY ........................................................ 1 2. DEFINITIONS ........................................................................ 2 3. DISCUSSION ........................................................................ 3 4. IMPLEMENTATION GUIDANCE ......................................................... 4 4.1 RECORDS TO BE GENERATED AND MAINTAINED ................................ 4 4.1.1 Individual Monitoring and Dose Records ........................................ 4 4.1.2 Monitoring and Workplace Records ............................................ 8 4.1.3 Administrative Records .................................................... 11 4.2 REPORTS ................................................................... 15 4.2.1 Reports to Individuals ...................................................... 16 4.2.2 Reports of Planned Special Exposures ......................................... 17 4.3 PRIVACY ACT CONSIDERATIONS .............................................. 17 4.3.1 Informing Individuals ...................................................... 17 4.3.2 Identifying Individuals ..................................................... 17 -
The International Commission on Radiological Protection: Historical Overview
Topical report The International Commission on Radiological Protection: Historical overview The ICRP is revising its basic recommendations by Dr H. Smith Within a few weeks of Roentgen's discovery of gamma rays; 1.5 roentgen per working week for radia- X-rays, the potential of the technique for diagnosing tion, affecting only superficial tissues; and 0.03 roentgen fractures became apparent, but acute adverse effects per working week for neutrons. (such as hair loss, erythema, and dermatitis) made hospital personnel aware of the need to avoid over- Recommendations in the 1950s exposure. Similar undesirable acute effects were By then, it was accepted that the roentgen was reported shortly after the discovery of radium and its inappropriate as a measure of exposure. In 1953, the medical applications. Notwithstanding these observa- ICRU recommended that limits of exposure should be tions, protection of staff exposed to X-rays and gamma based on consideration of the energy absorbed in tissues rays from radium was poorly co-ordinated. and introduced the rad (radiation absorbed dose) as a The British X-ray and Radium Protection Committee unit of absorbed dose (that is, energy imparted by radia- and the American Roentgen Ray Society proposed tion to a unit mass of tissue). In 1954, the ICRP general radiation protection recommendations in the introduced the rem (roentgen equivalent man) as a unit early 1920s. In 1925, at the First International Congress of absorbed dose weighted for the way different types of of Radiology, the need for quantifying exposure was radiation distribute energy in tissue (called the dose recognized. As a result, in 1928 the roentgen was equivalent in 1966). -
Rapport Du Groupe De Travail N° 9 Du European Radiation Dosimetry Group (EURADOS) – Coordinated Network for Radiation Dosimetry (CONRAD – Contrat CE Fp6-12684)»
- Rapport CEA-R-6220 - CEA Saclay Direction de la Recherche Technologique Laboratoire d’Intégration des Systèmes et des Technologies Département des Technologies du Capteur et du Signal Laboratoire National Henri Becquerel RADIATION PROTECTION DOSIMETRY IN MEDECINE REPORT OF THE WORKING GROUP N° 9 OF THE EUROPEAN RADIATION DOSIMETRY GROUP (EURADOS) COORDINATED NETWORK FOR RADIATION DOSIMETRY (CONRAD – CONTRACT EC N° FP6-12684) - Juin 2009 - RAPPORT CEA-R-6220 – «Dosimétrie pour la radioprotection en milieu médical – Rapport du groupe de travail n° 9 du European Radiation Dosimetry group (EURADOS) – Coordinated Network for Radiation Dosimetry (CONRAD – contrat CE fp6-12684)» Résumé - Ce rapport présente les résultats obtenus dans le cadre des travaux du WP7 (dosimétrie en radioprotection du personnel médical) de l’action coordonnée CONRAD (Coordinated Network for Radiation Dosimetry) subventionné par la 6ème FP de la communauté européenne. Ce projet a été coordonné par EURADOS (European RadiationPortection group). EURADOS est une organisation fondée en 1981 pour promouvoir la compréhension scientifique et le développement des techniques de la dosimétrie des rayonnements ionisant dans les domaines de la radioprotection, de la radiobiologie, de la thérapie radiologique et du diagnostic médical ; cela en encourageant la collaboration entre les laboratoires européens. Le WP7 de CONRAD coordonne et favorise la recherche européenne pour l'évaluation des expositions professionnelles du personnel sur les lieux de travail de radiologie thérapeutique et diagnostique. La recherche est organisée en sous-groupes couvrant trois domaines spécifiques : 1. Dosimétrie d'extrémité en radiologie interventionnelle et médecine nucléaire : ce sous- groupe coordonne des investigations dans les domaines spécifiques des hôpitaux et des études de répartition des doses dans différentes parties des mains, des bras, des jambes et des pieds ; 2. -
Industrial Radiography Exam Study Guide
State of Georgia Industrial Radiography Certifying Exam Study Guide The questions that follow are typical calculations that are performed in the field as part of radiographic operations. They include using the inverse square law to determine shielding thicknesses, dose rates, and restricted/unrestricted area boundaries. While these are similar in nature, these questions are NOT taken from previous Industrial Radiography Certifying Exams. Please concentrate on HOW to solve the problem, not just the final answer. Additionally, a knowledge of the Radioactive Materials Rules and Regulations, Chapter 391-3-17-.04, and an understanding of safe practices in the use of radiographic equipment, is required in order to perform well on the Certifying Exam. Please prepare accordingly. Inverse Square Law The inverse square law can be represented as follows: ( 2' ( 2 I1 D1 I2 D2 where I1 = the initial dose rate (in R/hr or mR/hr), D1 = the distance from the source where I1 is measured I2 = the second dose rate; units must be the same as I1 D2 = the distance from the source where I2 is measured; units must be the same as I2 This equation can be rearranged to isolate the desired variable. Half Value Layer (HVL) The half value layer (HVL) is the thickness of a given shielding material that will reduce to dose rate by half. For example, if there is a source emitting a dose rate of 50 mR/hr, and you put a HVL of a material between yourself and the source, the dose rate on the far side of the shielding material will be reduced to 25 mR/hr. -
Cost-Benefit Analysis and Radiation Protection* by J.U
Cost-Benefit Analysis and Radiation Protection* by J.U. Ahmed and H.T. Daw Cost-benefit analysis is a tool to find the best way of allocating resources. The International Commission on Radiological Protection (ICRP), in its publication No. 26, recommends this method in justifying radiation exposure practices and in keeping exposures as low as is reasonably achievable, economic and social considerations being taken into account 1. BASIC PHILOSOPHY A proposed practice involving radiation exposure can be justified by considering its benefits and its costs The aim is to ensure a net benefit. This can be expressed as: B = V-(P + X +Y) where: B is the net benefit; V is the gross benefit; P is the basic production cost, excluding protection; X is the cost of achieving the selected level of protection; and Y is the cost assigned to the detriment involved in the practice. If B is negative, the practice cannot be justified. The practice becomes increasingly justifiable at increasing positive values of B However, some of the benefits and detriments are intangible or subjective and not easily quantified. While P and X costs can be readily expressed in monetary terms, V may contain components difficult to quantify. The quantification of Y is the most problematic and probably the most controversial issue. Thus value judgements have to be introduced into the cost-benefit analysis. Such judgements should reflect the interests of society and therefore require the participation of competent authorities and governmental bodies as well as representative views of various sectors of the public. Once a practice has been justified by a cost-benefit analysis, the radiation exposure of individuals and populations resulting from that practice should be kept as low as reasonably achievable, economic and social factors being taken into account (i.e.