BS EN ISO 4037-1:2021
Radiological protection. X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Radiation characteristics and production methods
Standard number: | BS EN ISO 4037-1:2021 |
Pages: | 56 |
Released: | 2021-02-24 |
ISBN: | 978 0 539 14663 9 |
Status: | Standard |
BS EN ISO 4037-1:2021 - Radiological Protection Standard
Introducing the BS EN ISO 4037-1:2021, a comprehensive standard that is essential for professionals in the field of radiological protection. This standard provides detailed guidelines on the use of X and gamma reference radiation for calibrating dosemeters and doserate meters, as well as determining their response as a function of photon energy. Released on February 24, 2021, this document is a critical resource for ensuring accuracy and safety in radiological measurements.
Key Features of BS EN ISO 4037-1:2021
- Standard Number: BS EN ISO 4037-1:2021
- Pages: 56
- Release Date: February 24, 2021
- ISBN: 978 0 539 14663 9
- Status: Standard
Comprehensive Coverage
This standard is meticulously crafted to cover a wide range of topics related to radiological protection. It delves into the characteristics and production methods of X and gamma reference radiation, providing a robust framework for calibrating dosemeters and doserate meters. The document is structured to facilitate a deep understanding of how these instruments respond to different photon energies, ensuring that users can achieve precise and reliable measurements.
Why Choose BS EN ISO 4037-1:2021?
In the realm of radiological protection, precision and reliability are paramount. The BS EN ISO 4037-1:2021 standard is designed to meet these demands by offering:
- Expert Guidance: Developed by leading experts in the field, this standard provides authoritative guidance on the calibration and use of radiological instruments.
- Comprehensive Methodologies: It includes detailed methodologies for producing and characterizing reference radiation, ensuring that users can replicate and validate their measurements with confidence.
- Enhanced Safety: By adhering to the guidelines set forth in this standard, professionals can enhance the safety and accuracy of their radiological assessments, protecting both personnel and the environment.
Applications and Benefits
The BS EN ISO 4037-1:2021 standard is applicable across a variety of sectors where radiological protection is critical. These include medical facilities, nuclear power plants, research laboratories, and any other environment where radiation is present. By implementing the practices outlined in this standard, organizations can benefit from:
- Improved Measurement Accuracy: Achieve precise calibration of dosemeters and doserate meters, leading to more accurate radiation measurements.
- Regulatory Compliance: Ensure compliance with international radiological protection standards, reducing the risk of legal and regulatory issues.
- Operational Efficiency: Streamline radiological protection processes, saving time and resources while maintaining high safety standards.
Structure and Content
The document is organized into several sections, each focusing on a specific aspect of radiological protection. Key sections include:
- Introduction: An overview of the standard's purpose and scope.
- Radiation Characteristics: Detailed descriptions of the properties of X and gamma reference radiation.
- Production Methods: Guidelines for producing reference radiation with consistent and reliable characteristics.
- Calibration Procedures: Step-by-step instructions for calibrating dosemeters and doserate meters.
- Response Determination: Methods for assessing the response of instruments to varying photon energies.
Conclusion
The BS EN ISO 4037-1:2021 standard is an indispensable tool for professionals involved in radiological protection. Its comprehensive guidelines and expert insights ensure that users can achieve the highest levels of accuracy and safety in their work. Whether you are calibrating instruments, conducting research, or ensuring compliance with regulatory standards, this document provides the knowledge and methodologies needed to excel in the field of radiological protection.
Invest in the BS EN ISO 4037-1:2021 standard today and take a significant step towards enhancing the precision and reliability of your radiological measurements.
BS EN ISO 4037-1:2021
This standard BS EN ISO 4037-1:2021 Radiological protection. X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy is classified in these ICS categories:
- 17.240 Radiation measurements
This document specifies the characteristics and production methods of X and gamma reference radiation for calibrating protection-level dosemeters and doserate meters with respect to the phantom related operational quantities of the International Commission on Radiation Units and Measurements (ICRU)[5]. The lowest air kerma rate for which this standard is applicable is 1 µGy h–1. Below this air kerma rate the (natural) background radiation needs special consideration and this is not included in this document.
For the radiation qualities specified in Clauses 4 to 6, sufficient published information is available to specify the requirements for all relevant parameters of the matched or characterized reference fields in order to achieve the targeted overall uncertainty (k = 2) of about 6 % to 10 % for the phantom related operational quantities. The X ray radiation fields described in the informative Annexes A to C are not designated as reference X-radiation fields.
NOTE The first edition of ISO 4037‑1, issued in 1996, included some additional radiation qualities for which such published information is not available. These are fluorescent radiations, the gamma radiation of the radionuclide241Am, S-Am, and the high energy photon radiations R-Ti and R-Ni, which have been removed from the main part of this document. The most widely used radiations, the fluorescent radiations and the gamma radiation of the radionuclide241Am, S-Am, are included nearly unchanged in the informative Annexes A and B. The informative Annex C gives additional X radiation fields, which are specified by the quality index.
The methods for producing a group of reference radiations for a particular photon-energy range are described in Clauses 4 to 6, which define the characteristics of these radiations. The three groups of reference radiation are:
in the energy range from about 8 keV to 330 keV, continuous filtered X radiation;
in the energy range 600 keV to 1,3 MeV, gamma radiation emitted by radionuclides;
in the energy range 4 MeV to 9 MeV, photon radiation produced by accelerators.
The reference radiation field most suitable for the intended application can be selected from Table 1, which gives an overview of all reference radiation qualities specified in Clauses 4 to 6. It does not include the radiations specified in the Annexes A, B and C.
The requirements and methods given in Clauses 4 to 6 are targeted at an overall uncertainty (k = 2) of the dose(rate) value of about 6 % to 10 % for the phantom related operational quantities in the reference fields. To achieve this, two production methods are proposed:
The first one is to produce “matched reference fields”, whose properties are sufficiently well-characterized so as to allow the use of the conversion coefficients recommended in ISO 4037‑3. The existence of only a small difference in the spectral distribution of the “matched reference field” compared to the nominal reference field is validated by procedures, which are given and described in detail in ISO 4037‑2. For matched reference radiation fields, recommended conversion coefficients are given in ISO 4037‑3 only for specified distances between source and dosemeter, e.g., 1,0 m and 2,5 m. For other distances, the user has to decide if these conversion coefficients can be used. If both values are very similar, e.g., differ only by 2 % or less, then a linear interpolation may be used.
The second method is to produce “characterized reference fields”. Either this is done by determining the conversion coefficients using spectrometry, or the required value is measured directly using secondary standard dosimeters. This method applies to any radiation quality, for any measuring quantity and, if applicable, for any phantom and angle of radiation incidence. In addition, the requirements on the parameters specifying the reference radiations depend on the definition depth in the phantom, i.e., 0,07 mm, 3 mm and 10 mm, therefore, the requirements are different for the different depths. Thus, a given radiation field can be a "matched reference field" for the depth of 0,07 mm but not for the depth of 10 mm, for which it can then be a “characterized reference field”. The conversion coefficients can be determined for any distance, provided the air kerma rate is not below 1 µGy/h.
Both methods need charged particle equilibrium for the reference field. However, this is not always established in the workplace field for which the dosemeter is calibrated. This is especially true at photon energies without inherent charged particle equilibrium at the reference depth d, which depends on the actual combination of energy and reference depth d. Electrons of energies above 65 keV, 0,75 MeV and 2,1 MeV can just penetrate 0,07 mm, 3 mm and 10 mm of ICRU tissue, respectively, and the radiation qualities with photon energies above these values are considered as radiation qualities without inherent charged particle equilibrium for the quantities defined at these depths.
To determine the dose(rate) value and the associated overall uncertainty of it, a calibration of all measuring instruments used for the determination of the quantity value is needed which is traceable to national standards.
This document does not specify pulsed reference radiation fields.
Table 1
List of X and gamma reference radiation, their mean energies, , for 1 m distance and their short names
Radiation quality | keV | Radiation quality | keV | Radiation quality | keV | Radiation quality | keV | ||||
L-10 | 9,0 | N-10 | 8,5 | W-30 | 22,9 | H-10 | 8,0 | ||||
L-20 | 17,3 | N-15 | 12,4 | W-40 | 29,8 | H-20 | 13,1 | ||||
L-30 | 26,7 | N-20 | 16,3 | W-60 | 44,8 | H-30 | 19,7 | ||||
L-35 | 30,4 | N-25 | 20,3 | W-80 | 56,5 | H-40 | 25,4 | ||||
L-55 | 47,8 | N-30 | 24,6 | W-110 | 79,1 | H-60 | 38,0 | ||||
L-70 | 60,6 | N-40 | 33,3 | W-150 | 104 | H-80 | 48,8 | ||||
L-100 | 86,8 | N-60 | 47,9 | W-200 | 138 | H-100 | 57,3 | ||||
L-125 | 109 | N-80 | 65,2 | W-250 | 172 | H-150 | 78,0 | ||||
L-170 | 149 | N-100 | 83,3 | W-300 | 205 | H-200 | 99,3 | ||||
L-210 | 185 | N-120 | 100 | H-250 | 122 | ||||||
L-240 | 211 | N-150 | 118 | H-280 | 145 | ||||||
N-200 | 165 | H-300 | 143 | ||||||||
N-250 | 207 | H-350 | 167 | ||||||||
N-300 | 248 | H-400 | 190 | ||||||||
N-350 | 288 | ||||||||||
N-400 | 328 | ||||||||||
Radionuclides | High energy photon radiations | ||||||||||
Radiation quality | Radionuclide | keV | Radiation quality | Reaction | ; a MeV | ||||||
S-Cs | 137Cs | 662 | R-C | 12C (p,p'γ)12C | 4,2; 4,4 | ||||||
S-Co | 60Co | 1250 | R-F | 19F (p,αγ)16O | 4,4; 6,5 | ||||||
NOTE In the informative Annexes A to C, further radiation qualities are given. These cover the mean photon energies from 8 keV up to 270 keV. a Mean photon energy weighted by distribution of ambient dose equivalent, H*(10), with respect to photon energy E. |