ANSI N14.5-2014 Radioactive Materials - Leakage Tests on Packages for Shipment (INMM)《放射性原料.运输包装件泄露试验》.pdf

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1、 ANSI N14.5-2014 American National Standard For Radioactive Materials Leakage Tests on Packages for Shipment THIS PAGE INTENTIONALLY LEFT BLANK iii ANSI N14.5-2014 American National Standard for Radioactive Materials Leakage Tests on Packages for Shipment Secretariat Institute for Nuclear Materials

2、Management Approved June 19, 2014 American National Standards Institute, Inc. iv AMERICAN NATIONAL STANDARD Approval of an American National Standard requires review by ANSI that the requirements for due process, consensus, and other criteria for approval have been met by the standards developer. Co

3、nsensus is established when, in the judgment of the ANSI Board of Standards Review, substantial agreement has been reached by directly and materially affected interests. Substantial agreement means much more than a simple majority, but not necessarily unanimity. Consensus requires that all views and

4、 objections be considered, and that a concerted effort be made towards their resolution. The use of American National Standards is completely voluntary; their existence does not in any respect preclude anyone, whether he has approved the standards or not, from manufacturing, marketing, purchasing, o

5、r using products, processes, or procedures not conforming to the standards. The American National Standards Institute does not develop standards and will in no circumstances give interpretation on any American National Standard. Moreover, no person shall have the right or authority to issue an inter

6、pretation of an American National Standard in the name of the American National Standards Institute. Requests for interpretations should be addressed to the secretariat or sponsor whose name appears on the title page of this Standard. CAUTION NOTICE: This American National Standard may be revised or

7、 withdrawn at any time. The procedures of the American National Standards Institute require that action be taken periodically to reaffirm, revise, or withdraw this Standard. Purchasers of American National Standards may receive current information on all standards by calling or writing the American

8、National Standards Institute. Published by American National Standards Institute, Inc. 25 West 43rd Street, New York, NY 10036 Copyright 2014 by Institute for Nuclear Materials Management All rights reserved. No part of this publication may be reproduced in any form, in an electronic retrieval syste

9、m or otherwise, without prior written permission of the publisher. Printed in the United States of America v Contents Foreword vi 1. Scope and Field of Application 1 2. Definitions, Symbols, and Units . 3 3. Containment Criteria . 7 4. Procedure for Meeting the Requirements of this Standard . 9 5. D

10、etermination of Allowable Release Rates 11 6. Determination of Allowable and Reference Air Leakage Rates . 13 7. Test Requirements 15 8. Conduct of Tests . 19 9. References . 21 Appendices Appendix A - Leakage Test Methods and Procedures . 23 Appendix B - Basic Data 41 Appendix C - Releasable Homoge

11、nous Mixture Relationships . 73 Figures Figure 1. How to use this Standard. 9 Tables Table 1. Containment Boundary Test Requirements 16! Table A-1. Summary of Leakage Tests . 27! Table A-1. Summary of Leakage Tests (cont.) 28! Table A-1. Summary of Leakage Tests (cont.) 29! Table A-2. Leakage Test S

12、ensitivities . 30! Table B-1. Properties for Some Common Gases (at 298K and 1 atm abs) 44! Table B-2. Upstream Air Leakage for Various Hole Diameters (a = 1 cm, T u= 298K) 44! Table B.15.2-1 49! Table B.15.2-2 49! Table B.15.21-1 59! Table B.15.21-2 60! Table B.15.25-1 62! Table B.15.25-2 63! Table

13、B.15.27-1 66! Table B.15.27-2 66! Table B.15.32-1 70! Table B.15.32-2 70! vi Foreword (This foreword is not part of American National Standard N14.5-2014) The Accredited Standards Committee on Packaging and Transportation of Radioactive and Non-Nuclear Hazardous Materials, N14, under whose jurisdict

14、ion this Standard was developed, has the following scope: Standards for the packaging and transportation of fissile and radioactive materials, non-nuclear hazardous materials, including waste and mixed materials, but not including movement or handling during processing and manufacturing operations.

15、This revision supersedes American National Standard For Radioactive Materials Leakage Tests on Packages for Shipment, ANSI N14.51997. The revised Standard provides acceptable methods for demonstrating that Type B packages designed for transport of normal-form radioactive material comply with the reg

16、ulatory containment requirements specified in Title 10 of the Code of Federal Regulations, Part 71. To assist a user in meeting regulatory requirements, the Standard describes methods for converting regulatory requirements to allowable leakage rates. Use of these rates will facilitate demonstrating

17、that a Type B package complies with the regulatory requirements during the package design, fabrication, maintenance, periodic, and pre-shipment phases. The standard also provides guidance to account for the physical form of the escaping medium, its physical properties, and conditions under which the

18、 medium escapes. The medium may contain radioactive material in gaseous, liquid, or solid forms. Many leakage test procedures are available, but the appropriate procedure will depend on its sensitivity and its applicability to the specific package. The package designer or shipper must assess the con

19、centration of radioactive materials that might escape from the package, under shipping conditions, so that a leakage test procedure with adequate sensitivity can be selected. An important aspect of this Standard is the use of the term leaktight. In this Standard, leaktight is defined as that degree

20、of package containment that in a practical sense precludes any radiologically significant release of radioactive materials. Finally, this Standard was completely reviewed during the 2014 revision. Definitions have been added for containment boundary, standard conditions and tracer gas, as well as de

21、finitions related to calibration. The fabrication leakage rate test components have been clarified to include the base material. Guidance has been added to include packaging design considerations and leakage rate test selection methods, as well as the use of test fixtures in fabrication and periodic

22、 leakage rate testing. Leakage rate testing performance and quality assurance guidance have also been updated. Guidance has been removed relating to packages required to provide double containment. In Appendix A, guidance was added to encourage the use of a Leak Test Engineer or a Leak Test Level II

23、I during design and testing. The use of standard leaks was expanded upon, guidance was added to several leak test methods, and the term “soap bubble” was changed to “bubble” due to recognition that commercial soap may cause a false-negative test result. In Appendix B, examples were reworked which ch

24、anged the results of several examples. In Appendix C, the calculation of the A 2value for the releasable materials was corrected. Throughout the Standard and appendices typographical errors were corrected.Regulatory authorities may accept or reject any or all parts of this Standard, and may require

25、other leakage test provisions not addressed in this Standard. This document contains three informative appendices that are not considered part of this Standard. Suggestions for improvement of this Standard will be welcome. They should be sent to the Institute of Nuclear Materials Management, 111 Dee

26、r Lake Road, Suite 100, Deerfield, IL 60015, USA. This Standard was prepared and approved for submittal to ANSI by the Accredited Standards Committee on Packaging and Transportation of Radioactive and Non-Nuclear Hazardous Material, N14. Committee approval of the standard does not necessarily imply

27、that all committee members voted for its approval. At the time it approved this Standard, the N14 Committee comprised the following members. vii N14 Executive Committee N14 Chair Matthew R. Feldman N14 Vice-Chair William H. Lake N14 Secretary Ronald B. Natali Organization Represented Name of Represe

28、ntative Commercial Vehicle Safety Alliance C. Smith Health Physics Society R. A. Parker U.S. Department of Energy . A.K. Kapoor U.S. Department of Transportation . R. Boyle U.S. DOE National Nuclear Security Administration . A. Al-Daouk U.S. Nuclear Regulatory Commission . M. Sampson Individual Memb

29、ers Al-Daouk, Ahmad M. Gregory, Phillip C., P.E. Porter, Steven A. Araniz, Enrique (Rick) A. Grella, Alfred W. Rawl, Richard R. Bayley, Donna Hawk, Mark B. Rummell, Trevor Bellamy, J. Stephen Hummer, James H. Rymer, Andrew C. Bennett, David R. Johnston, James R. Smith, Carlisle Bennett, Marvin E. Ka

30、poor, Ashok Sampson, Michele Bentz, Dr. Edward Kavanagh, Jackie Shelton, Thomas A. Best, Ralph E. Lake, William H. Shuler, Dr. James M Boyle, Richard Lambert, David T. Stern, Larry D. Campbell, Mark Lambert, Mark T. Thomas, David C. Castagnacci, Albert E. McNeil, Ella Vaughan, Dr. Robert A. Charette

31、, Marc-Andre Mohamed, Dr. Ashraf Viebrock, James M. Clark, Gary L., P.E. Nelson, Dr. Kevin Wakeman, Brian H. Darrough, Dr. M. Elizabeth Nolan, Donald J. Walker, Randy Eyre, Phillip OConnor, Stephen C. Wangler, Michael E. Falci, Frank Opperman, Erich Warriner, Doyle J. Feldman, Matthew R. Parker, Dr.

32、 Roy Fischer, Larry E., P.E. Pope, Ronald B. Members of the N14.5 Subcommittee Leakage Tests on Packages for Shipment of Radioactive Materials Co-Chairs L.E. Fisher and P.C. Gregory Vice-Chair T.E. Sellmer Principal Editor R. S. Hafner Web Administrator T.E. Sellmer Subcommittee Members M. E. Bennet

33、t W. H . Lake J. M. Shuler P. S. Blanton N. L. Osgood S-W. Tam J. S. Ireland P. B. Shaw M. H. West viii This page intentionally left blank 1 AMERICAN NATIONAL STANDARD ANSI N14.5-2014 American National Standard for Radioactive MaterialsLeakage Tests on Packages for Shipment 1. Scope and Field of App

34、lication This Standard specifies methods for demonstrating that Type B packages designed for transport of normal form radioactive material comply with the containment requirements of Title 10 of the Code of Federal Regulations Part 71 (10 CFR Part 71). This Standard describes Package release limits

35、Methods for relating package release limits to allowable and reference leakage rates Minimum requirements for leakage rate test procedures. This Standard provides requirements for the following leakage rate tests Design Fabrication Maintenance Periodic Pre-shipment. This Standard also contains non-m

36、andatory appendices on leakage rate test methods, determination of reference leakage rates, and determinations of activity in the medium. ANSI N14.5-2014 2 This page intentionally left blank. ANSI N14.5-2014 3 2. Definitions, Symbols, and Units 2.1 Definitions Terms defined in the applicable documen

37、ts in Section 3 have the same meaning in this Standard. Additional terms have been defined particularly for the purpose of this Standard and may not conform to those in other publications. A 2 : A quantity (activity) of radioactive material specified in 10 CFR Part 71 and used to calculate the allow

38、able release rate. Allowable leakage rate: The maximum permissible volume of fluid leaking from the containment system per unit of time (see Leakage rate) for either normal conditions of transport, L N , or hypothetical accident conditions, L A . Allowable release rate: The maximum permissible quant

39、ity of radioactive material escaping from the containment system per unit of time (see Release rate) for either normal conditions of transport, R N , or hypothetical accident conditions, R A . Calibrated leak: (see Standard leak). Calibration: (see Instrument calibration, and System calibration, and

40、 Calibration factor). Calibration factor: The calibration factor (i.e., the CF) is the factor that corrects a leak detector instrument response to correspond to the known leakage rate from a Standard leak applied to a Test system. The CF is calculated from the leak detector response recorded during

41、the System calibration. Containment boundary: The designated boundary of the containment system, which is designed to prevent leakage of radioactive material. The containment boundary may include the containment vessel shell, welds, seals, lids, cover plates, and valves. Containment system: The asse

42、mbly of the components that comprise the packaging intended to retain the radioactive material (radioactive contents) during transport. Hypothetical accident conditions: The hypothetical accident test conditions for Type B packages specified in 10 CFR Part 71. Instrument Calibration (gas species spe

43、cific leak detectors): The process of tuning a leak detector to distinguish the tracer gas from other gas species, and calibrating the output of the instrument relative to a Standard leak. Leak: Any opening through a containment boundary that permits the passage of fluid. Leakage rate: The volume of

44、 fluid passing through a containment boundary per unit of time. Leaktight: The degree of package containment that, in a practical sense, precludes any significant release of radioactive materials. This degree of containment is achieved by demonstration of a leakage rate less than or equal to 1 10 -7

45、ref cm 3 /s, of air at an upstream pressure of 1 atmosphere (atm) absolute (abs), and a downstream pressure of 0.01 atm abs or less. Medium: Any fluid that could transport radioactive material through a leak. Normal conditions of transport: The normal transport test conditions for Type B packages sp

46、ecified in 10 CFR Part 71. Normal form radioactive material: Radioactive material as specified in 10 CFR Part 71. Package: The packaging, together with its radioactive contents, as presented for transport. Packaging: The assembly of components necessary to ensure compliance with the packaging requir

47、ements of 10 CFR Part 71. ANSI N14.5-2014 4 Permeation: The passage of a gas through a containment boundary by adsorption, diffusion, and desorption mechanisms. Reference air leakage rate: The allowable leakage rate converted to reference cubic centimeters per second (refcm 3 /s). Note: for this Sta

48、ndard, a reference air leakage rate greater than 1 10 -1ref cm 3 /s shall be treated as 1 10 -1refcm 3 /s and a leakage rate less than 1 10 -7ref cm 3 /s shall be treated as 1 10 -7ref cm 3 /s. Reference cubic centimeter per second (ref cm 3 /s): A unit of leakage rate of one cubic centimeter of dry

49、 air per second at 1 atmosphere absolute pressure (760 mm Hg) and 25C. Release: Any escape of radioactive material from the containment system. Release fraction: The portion of the radioactive contents considered to be available for release from the containment system. Release rate: Release per unit of time. Response time: For leakage rate test methods utilizing an evacuated volume (e.g., gas filled envelope- hood, evacuated envelope), the response time is the elapsed time required for a Test system to yield a stable (