ANSI N43.17-2009 Radiation Safety for Personnel Security Screening Systems Using X-ray or Gamma Radiation《使用X-射线或γ辐射的个人安全防护系统的辐射安全性》.pdf
《ANSI N43.17-2009 Radiation Safety for Personnel Security Screening Systems Using X-ray or Gamma Radiation《使用X-射线或γ辐射的个人安全防护系统的辐射安全性》.pdf》由会员分享,可在线阅读,更多相关《ANSI N43.17-2009 Radiation Safety for Personnel Security Screening Systems Using X-ray or Gamma Radiation《使用X-射线或γ辐射的个人安全防护系统的辐射安全性》.pdf(46页珍藏版)》请在麦多课文档分享上搜索。
1、ANSI/HPS N43.17-2009 American National Standard Radiation Safety for Personnel Security Screening Systems Using X-Ray or Gamma Radiation Approved: August 2009 American National Standards Institute, Inc. iiPublished by Health Physics Society 1313 Dolley Madison Blvd. Suite 402 McLean, VA 22101 Copyri
2、ght 2009 by the Health Physics Society. All rights reserved. No part of this publication may be reproduced in any form, in an electronic retrieval system or otherwise, without prior written permission of the publisher. Printed in the United States of America iiiThe Health Physics Society N43.17 Stan
3、dards Subcommittee responsible for the development of N43.17-2002 had the following members: Frank Cerra (chair), Martin Annis, Edgar Bailey, Terry Brayer, Larry Cothran, Daniel Kassiday, Andy Kotowski, Roy Lindquist, William Passetti, Richard Schueller, Timothy Scroggins, Gerald Smith, Steve Smith,
4、 Richard Whitman, Pamela Zaresk. The N43.17 Subcommittee responsible for the current revision had the following members: Frank Cerra, Co-Chair, National Institute of Standards and Technology Daniel Kassiday, Co-Chair, Food and Drug Administration Martin Annis, Annistech Paul Bergstrom, National Inst
5、itute of Standards and Technology Jack Burroughs, L-3 Security NCRP Commentary 16; 2003. AMERICAN NATIONAL STANDARD ANSI/HPS N43.17-2009 1 Radiation Safety for Personnel Security Screening Systems Using X-Ray or Gamma Radiation 1.0 Scope This standard applies to the manufacture and operation of secu
6、rity screening systems that are intended to expose humans to primary beam x-rays, gamma radiation, or both. This standard does not address neutron-based systems. Examples of screening practices covered by this standard include the following: Direct screening of humans to detect objects hidden within
7、 an individuals body or clothing. Knowingly exposing human occupants to the primary beam when screening vehicles or structures. Screening of orthopedic casts and prosthetic devices while being worn. The standard provides requirements specific to the ionizing radiation safety aspects of both the desi
8、gn and operation of these systems. It does not include electrical safety guidelines or any other safety, performance, or use considerations outside the realm of radiation safety. The limits in this standard are not intended to apply to stowaways not authorized to be in the area and not known to be p
9、resent prior to scanning. It is recognized that the need for security might sometimes call for exceeding the dose limits set in this standard. This should be based on an analysis demonstrating that the security benefit outweighs the risk from the radiation exposure incurred by the individuals screen
10、ed. This standard does not address the evaluation of the societal benefit of security screening. Therefore, screening operations that exceed this standards dose limits are beyond the scope of this standard and shall not claim compliance with this standard. Medical diagnostic systems should be used u
11、nder medical supervision and are not covered by this standard. 2.0 Definitions The following are terms that are either of key significance or have a specific meaning in this standard that might differ from the terms usage elsewhere. This is not meant to be a comprehensive glossary of terms used in r
12、adiation protection. The discussion in Annex C contains additional information on radiation quantities and units. Access panel: Any panel designed to be removed or opened for maintenance or service purposes that when removed or opened affects the radiation leakage pattern or allows intrusion into th
13、e radiation field. ADAP: see Ambient Dose Equivalent Area Product Administrative control: A documented, compulsory, routine procedure aimed at controlling the radiation exposure received by individuals and ensuring that the appropriate dose limits are not exceeded. Air kerma: The total initial kinet
14、ic energy transferred to charged particles per mass of air as a result of irradiation. The unit of air kerma is the joule per kilogram or gray (Gy). (1 Gy air kerma corresponds to approxi-mately a 114-roentgen exposure). ALARA: As Low As Reasonably Achievable, economic and social factors being taken
15、 into account. Aluminum-equivalent filtration: The thickness of aluminum affording the same attenuation of the x-ray beam as the material in question under specified conditions. Ambient dose equivalent area product (ADAP): The product of the ambient dose equivalent, H*(10), and the scan area at a de
16、fined distance (used only for partial-body scanners). Ambient dose equivalent, H*(d): The dose equivalent at a point in a radiation field produced by the corresponding expanded and aligned field in the ICRU sphere (ICRU ANSI/HPS N43.17-2009 2 1998) at a depth d on the radius opposing the direction o
17、f the aligned field. Dose equivalent is the product of the absorbed dose D at a point in tissue (i.e., the mean energy imparted per unit mass) and the quality factor Q at that point. The unit of dose equivalent, H, and of ambient dose equivalent, H*(d), is the joule per kilogram (J kg1), with the sp
18、ecial name sievert (Sv, 1 Sv = 100 rem). Backscatter system: A security screening system that makes use of radiation scattered or deflected from an object or person to form an image of the scattering object or person. Beam exit surface: The surface of the outer system assembly from which the direct
19、x-ray or gamma ray beam emanates. This may be a flat surface or the outer surface of a port or collimator. The subject being scanned is exposed through this surface. Systems with more than one radiation source may have more than one beam exit surface. Beam stop: A radiation shield meant to intercept
20、 the direct beam of radiation. Bystander: Any person other than the individual being screened who is not directly associated with operation of the system. Effective dose: A summation of the equivalent doses in tissues or organs each multiplied by the appropriate tissue weighting factor as defined by
21、 the International Commission on Radiation Units and Measurements (ICRU 1998). The tissue weighting factors were modified by the International Commission on Radiological Protection in its Publication 103 (ICRP 2007). The unit of effective dose is joule per kilogram, and its special name is sievert (
22、Sv, 1 Sv = 100 rem). Engineering control: A safety component of the system design that prevents improper operation or unintended radiation exposure. Examples of engineering controls include one-way turnstiles, interlocked motion sensors, etc. Equivalent dose: The absorbed dose in an organ or tissue
23、multiplied by the appropriate radiation weighting factor. The unit of equivalent dose is joule per kilogram, and its special name is sievert (Sv, 1 Sv = 100 rem). See ICRU (1998). External surface: The outside surface of the enclosure containing all associated ionizing radiation sources. Facility: S
24、ee Operating facility. General-use system: A personnel screening system that delivers a reference effective dose equal to or less than 0.25 Sv (25 rem) per screening as defined in this standard. Given proper justification and certain restrictions, general-use systems may be operated without specific
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