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ASTM E2303-11e1

(Guide)

Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities

Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities

SIGNIFICANCE AND USE
4.1 This guide is one of a set of guides and practices that provide recommendations for properly implementing dosimetry in radiation processing. In order to understand and effectively use this and other dosimetry standards, consider first “Practice for Dosimetry in Radiation Processing,” ASTM Practice E2628, which describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E10.01 series of dosimetry standards. In addition, ASTM Practice E2628 provides guidance on the selection of dosimetry systems and directs the user to other standards that provide information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.  
4.2 Radiation processing is carried out under fixed path conditions where (a) a process load is automatically moved through the radiation field by mechanical means or (b) a process load is irradiated statically by manually placing product at predetermined positions before the process is started. In both cases the process is controlled in such a manner that the process load position(s) and orientation(s) are reproducible within specified limits.Note 2—Static irradiation encompasses irradiation of the process load using either manual rotation, no rotation or automated rotation.  
4.3 Some radiation processing facilities that utilize a fixed conveyor path for routine processing may also characterize a region within the radiation field for static radiation processing, sometimes referred to as “Off Carrier” processing.  
4.4 Many radiation processing applications require a minimum absorbed dose (to achieve a desired effect or to fulfill a legal requirement), and a maximum absorbed dose (to ensure that the product, material or substance still meets functional specifications or to fulfill a legal requirement).  
4.5 Information from the dose mapping is used to:  
4.5.1 Characterize the radiation process and assess the reproducibility of absorbe...
SCOPE
1.1 This document provides guidance in determining absorbed-dose distributions (mapping) in products, materials or substances irradiated in gamma, X-ray (bremsstrahlung) and electron beam facilities. Note 1—For irradiation of food and the radiation sterilization of health care products, specific ISO and ISO/ASTM standards containing dose mapping requirements exist. See ISO/ASTM Practices 51431, 51608, 51649, 51702 and 51818 and ISO 11137-1. Regarding the radiation sterilization of health care products, in those areas covered by ISO 11137-1, that standard takes precedence.  
1.2 This guide is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing. it is intended to be read in conjunction with ASTM Practice E2628.  
1.3 Methods of analyzing the dose map data are described. Examples are provided of statistical methods that may be used to analyze dose map data.  
1.4 Dose mapping for bulk flow processing and fluid streams is not discussed.  
1.5 Dosimetry is an element of a total quality management system for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.  
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory requirements prior to use.

General Information

Status
Historical
Publication Date
30-Jun-2011
ICS
13.280 - Radiation protection
Technical Committee
E61 - Radiation Processing
Drafting Committee
E61.03 - Dosimetry Application
Current Stage
Ref Project

Relations

Replaces
ASTM E2303-11 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
Effective Date
01-Jul-2011
Replaced By
ASTM ISO/ASTM52303-15 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
Effective Date
09-Feb-2015
Referred By
ASTM ISO/ASTM51702-13(2021) - Standard Practice for Dosimetry in a Gamma Facility for Radiation Processing
Effective Date
01-Jul-2011
Referred By
ASTM ISO/ASTM51608-15(2022) - Standard Practice for Dosimetry in an X-Ray (Bremsstrahlung) Facility for Radiation Processing at Energies between 50 keV and 7.5 MeV
Effective Date
01-Jul-2011
Referred By
ASTM ISO/ASTM51649-15 - Standard Practice for Dosimetry in an Electron Beam Facility for Radiation Processing at Energies Between 300 keV and 25 MeV
Effective Date
01-Jul-2011

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ASTM E2303-11e1 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing FacilitiesASTM E2303-11e1 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
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ASTM E2303-11e1 - Standard Guide for Absorbed-Dose Mapping in Radiation Processing Facilities
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NOTICE: This standard has either been superseded and replaced by a new version or withdrawn.
Contact ASTM International (www.astm.org) for the latest information
´1
Designation: E2303 − 11 AnAmerican National Standard
Standard Guide for
1
Absorbed-Dose Mapping in Radiation Processing Facilities
This standard is issued under the fixed designation E2303; the number immediately following the designation indicates the year of
original adoption or, in the case of revision, the year of last revision.Anumber in parentheses indicates the year of last reapproval.A
superscript epsilon (´) indicates an editorial change since the last revision or reapproval.
1
ε NOTE—Editorial changes were made throughout in December 2012.
1. Scope E170Terminology Relating to Radiation Measurements and
Dosimetry
1.1 This document provides guidance in determining
E178Practice for Dealing With Outlying Observations
absorbed-dose distributions (mapping) in products, materials
E2232Guide for Selection and Use of Mathematical Meth-
orsubstancesirradiatedingamma,X-ray(bremsstrahlung)and
ods for CalculatingAbsorbed Dose in Radiation Process-
electron beam facilities.
ing Applications
NOTE1—Forirradiationoffoodandtheradiationsterilizationofhealth
E2628Practice for Dosimetry in Radiation Processing
care products, specific ISO and ISO/ASTM standards containing dose
mapping requirements exist. See ISO/ASTM Practices 51431, 51608,
2
2.2 ISO/ASTM Standards:
51649, 51702 and 51818 and ISO 11137-1. Regarding the radiation
51261Guide for Selection and Calibration of Dosimetry
sterilization of health care products, in those areas covered by ISO
Systems for Radiation Processing
11137-1, that standard takes precedence.
51431Practice for Dosimetry in Electron Beam and X-Ray
1.2 This guide is one of a set of standards that provides
(Bremsstrahlung) Irradiation Facilities for Food Process-
recommendations for properly implementing dosimetry in
ing
radiation processing. it is intended to be read in conjunction
51608Practice for Dosimetry in an X-ray (Bremsstrahlung)
with ASTM Practice E2628.
Facility for Radiation Processing
1.3 Methods of analyzing the dose map data are described.
51649Practice for Dosimetry in an Electron Beam Facility
Examples are provided of statistical methods that may be used
forRadiationProcessingatEnergiesbetween300keVand
to analyze dose map data.
25 MeV
51702Practice for Dosimetry in a Gamma Irradiation Facil-
1.4 Dose mapping for bulk flow processing and fluid
streams is not discussed. ity for Radiation Processing
51707Guide for Estimating Uncertainties in Dosimetry for
1.5 Dosimetry is an element of a total quality management
Radiation Processing
system for an irradiation facility. Other controls besides do-
51818Practice for Dosimetry in an Electron Beam Facility
simetry may be required for specific applications such as
for Radiation Processing at Energies between 80 and 300
medical device sterilization and food preservation.
keV
1.6 This standard does not purport to address all of the
2.3 International Commission on Radiation Units and Mea-
safety concerns, if any, associated with its use. It is the
3
surements Reports:
responsibility of the user of this standard to establish appro-
ICRU Report 60Fundamental Quantities and Units for
priate safety and health practices and determine the applica-
Ionizing Radiation
bility of regulatory requirements prior to use.
4
2.4 International Organization for Standardization:
2. Referenced Documents
ISO 11137-1Sterilization of health care products – Radia-
2
tion – Part 1: Requirements for development, validation,
2.1 ASTM Standards:
and routine control of a sterilization process for medical
devices
1
This guide is under the jurisdiction of ASTM Committee E61 on Radiation
GUM Guide to the Expression of Uncertainty in
Processingand is the direct responsibility of Subcommittee E61.03 on Dosimetry
Measurement, 1995, ISBN 92-6710188-9
Application.
Current edition approved July 1, 2011. Published August 2011. Originally
approved in 2003. Last previous edition approved in 2003 as E2303-03. DOI:
10.1520/E2303-11E01.
2 3
For referenced ASTM and ISO/ASTM standards, visit the ASTM website, Available from International Commission on Radiation Units and
www.astm.org, or contact ASTM Customer Service at service@astm.org. For Measurements, 7910 Woodmont Ave., Suite 800, Bethesda, MD 20814.
4
Annual Book of ASTM Standards volume information, refer to the standard’s Available from International Organization for Standardization (ISO), 1 rue de
Document Summary page on the ASTM website. Varembé, Case postale 56, CH-1211, Geneva 20, Switzerland.
Copyright © ASTM International, 100 Barr Harbor Drive, PO Box C700, West Conshohocken, PA 19428-2959. United States
1

---------------------- Page: 1 ----------------------
´1
E2303 − 11
VIMInternational Vocabulary of Basic and General Terms 3.1.13 routine monitoring position—position where ab-
in Metrology sorbed dose is monitored during routine processing to ensure
tha
...

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5.2 The test is suitable for application to natural minerals, simulated waste form materials, and radioactive waste form material specimens.  
5.3 Data from this test may form part of the larger body of data that is necessary in the logical approach to long-term prediction of waste form behavior, as described in Practice C1174. In particular, measured solution concentrations and characterizations of altered surfaces may be used in the validation of geochemical modeling codes.  
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1.1 These test methods cover procedures for the determination of weight percent volatile content of coatings, inks, and adhesives designed to be cured by exposure to ultraviolet light or to a beam of accelerated electrons.  
1.2 Test Method A is applicable to radiation curable materials that are essentially 100 % reactive but may contain traces (no more than 3 %) of volatile materials as impurities or introduced by the inclusion of various additives.  
1.3 Test Method B is applicable to all radiation curable materials but must be used for materials that contain volatile solvents intentionally introduced to control application viscosity and which are intended to be removed from the material prior to cure.  
1.4 These test methods may not be applicable to radiation curable materials wherein the volatile material is water, and other procedures may be substituted by mutual consent of the producer and user.  
1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.  
1.6 This standard does not purport to address all of the safety problems, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. A specific hazard statement is given in 15.7.  
1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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ASTM
ASTM E1167-15(2021)(Guide)
Standard Guide for Radiation Protection Program for Decommissioning Operations

SIGNIFICANCE AND USE
4.1 A program based on this guide will provide assurance to all concerned that the appropriate elements of radiation safety have been included to protect workers, the general public, and the environment in proximity to the decommissioning activities.  
4.2 Implementation of such a program will provide assurance to those agencies responsible for review or audit of the decommissioning project that the requirements for radiation protection have been addressed.
SCOPE
1.1 This guide provides instruction to the individual charged with the responsibility for developing and implementing the radiation protection program for decommissioning operations.  
1.2 This guide provides a basis for the user to develop radiation protection program documentation that will support both the radiological engineering and radiation safety aspects of the decommissioning project.  
1.3 This guide presents a description of those elements that should be addressed in a specific radiation protection plan for each decommissioning project. The plan would, in turn, form the basis for development of the implementation procedures that execute the intent of the plan.  
1.4 This guide applies to the development of radiation protection programs established to control exposures to radiation and radioactive materials associated with the decommissioning of nuclear facilities. The intent of this guide is to supplement existing radiation protection programs as they may pertain to decommissioning workers, members of the general public and the environment by describing the basic elements of a radiation protection program for decommissioning operations.  
1.5 This guide defines the elements of a radiation protection program that will ensure that the goals and objectives of a decommissioning activity are attained within the radiological limits and restrictions imposed by applicable governing and regulating agencies. The implementation of such a program will provide radiological protection to personnel and the environment. This guide should be used for developing the documentation that defines the intent and implementation of the radiation protection program for a specific decommissioning project.  
1.6 The Radiation Protection Program should address the following elements (see Note 1). This program shall be developed and maintained such that it satisfies all applicable Quality Assurance requirements developed for the decommissioning project.  
Note 1: If the site to be decommissioned is adjacent to an operating site, the radiological impact of the operating site must be considered in the development of the Radiation Protection Program for the decommissioning site.  
1.7 This guide does not address the subjects of emergency preparedness, safeguards, accountability, waste handling, storage, and transportation. Each of these issues has a direct interface with the radiation protection program. However, each constitutes a program in and of itself from program definition through implementation.  
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.  
1.9 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.

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