BS ISO 4037-2-1998 X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Dosimetry for rat.pdf
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1、BRITISH STANDARD BSISO 4037-2:1997 X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Part 2: Dosimetry for radiation protection over the energy ranges8keV to1,3MeV and4MeV to9MeV ICS 17.240BSISO4037-2:1997
2、 This British Standard, having been prepared under the directionof the Engineering SectorBoard, was published underthe authority of the Standards Board and comes intoeffect on 15 March1998 BSI 05-1999 ISBN 0 580 29311 4 National foreword This British Standard reproduces verbatim ISO4037-2:1997 and i
3、mplements it as the UK national standard. It supersedes BS5869:1980 which is withdrawn. The UK participation in its preparation was entrusted to Technical Committee NCE/2, Health physics instrumentation, which has the responsibility to: aid enquirers to understand the text; present to the responsibl
4、e international/European committee any enquiries on the interpretation, or proposals for change, and keep the UK interests informed; monitor related international and European developments and promulgate them in the UK. A list of organizations represented on this committee can be obtained on request
5、 to its secretary. Cross-references The British Standards which implement international or European publications referred to in this document may be found in the BSI Standards Catalogue under the section entitled “International Standards Correspondence Index”, or by using the “Find” facility of the
6、BSI Standards Electronic Catalogue. A British Standard does not purport to include all the necessary provisions of a contract. Users of British Standards are responsible for their correct application. Compliance with a British Standard does not of itself confer immunity from legal obligations. Summa
7、ry of pages This document comprises a front cover, an inside front cover, pages i and ii, theISOtitle page, pages ii to iv, pages 1 to 25 and a back cover. This standard has been updated (see copyright date) and may have had amendments incorporated. This will be indicated in the amendment table on t
8、he inside front cover. Amendments issued since publication Amd. No. Date CommentsBSISO4037-2:1997 BSI 05-1999 i Contents Page National foreword Inside front cover Foreword iii Text of ISO 4037-2 1ii blankBSISO4037-2:1997 ii BSI 05-1999 Contents Page Foreword iii Introduction 1 1 Scope 1 2 Normative
9、references 1 3 Definitions 1 4 Apparatus 4 5 General procedures 4 6 Procedures applicable to ionization chambers 5 7 Additional procedures and precautions specific to gamma radiation dosimetry using radionuclide sources 7 8 Additional procedures and precautions specific to X-radiation dosimetry 8 9
10、Special procedures and precautions specific to fluorescence X-radiation Limitation of extraneous radiation in beams 9 10 Dosimetry of reference radiation at photon energies between4MeV and9MeV 10 11 Uncertainty of measurement 19 Annex A (informative) Determination by ionization chamber measurements
11、of air kerma under receptor-absent conditions and of absorbed dose to tissue (water) under receptor conditions 21 Annex B (informative) Bibliography 23 Figure 1 Example of a typical X-ray setup 9 Figure 2 Example of setup for calibration of fluence detectors by means of associated particle counting
12、19 16 Figure 3 Radiation geometries for in-phantom measurements, showing cross-sections through two types of phantom: a sphere of30cm diameter and a parallelepiped of30cm 30cm 20cm 17 Table 1 Typical values for the bremsstrahlung correction 12 Table 2 Values for attenuation and scatter correction, k
13、 att , for different types of ionization chamber 13 Table 3 Typical average restricted-mass collision-stopping powers of air relative to those of the wall materials 13 Table 4 Typical energy absorption coefficients for non air-equivalent wall materials relative to air 15 14 Descriptors: Nuclear radi
14、ation, radiation protection, radiation measuring instruments, exposure dose-rate meters, calibration, reference sources, gamma radiation, X rays, dosimetry.BSISO4037-2:1997 BSI 05-1999 iii Foreword ISO (the International Organization for Standardization) is a worldwide federation of national standar
15、ds bodies (ISO member bodies). The work of preparing International Standards is normally carried out through ISO technical committees. Each member body interested in a subject for which a technical committee has been established has the right to be represented on that committee. International organi
16、zations, governmental and non-governmental, in liaison with ISO, also take part in the work. ISO collaborates closely with the International Electrotechnical Commission (IEC) on all matters of electrotechnical standardization. Draft International Standards adopted by the technical committees are cir
17、culated to the member bodies for voting. Publication as an International Standard requires approval by at least75% of the member bodies casting a vote. International Standard ISO4037-2 was prepared by Technical Committee ISO/TC85, Nuclear energy, Subcommittee SC2, Radiation protection. This first ed
18、ition of ISO4037-2, along with ISO4037-1, cancels and replaces the first edition of ISO4037:1979, which has been technically revised. ISO4037 consists of the following parts, under the general title X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining th
19、eir response as a function of photon energy. Part 1: Radiation characteristics and production methods; Part 2: Dosimetry of X and gamma reference radiation for radiation protection over the energy ranges8keV to1,3MeV and4MeV to9MeV; Part 3: Calibration of area and personal dosemeters. Annex A and An
20、nex B of this part of ISO4037 are for information only.iv blank BSI 05-1999 1 BSISO4037-2:1997 Introduction The term “dosimetry” is used in this part of ISO4037 to describe the method by which the value of a physical quantity characterizing the interaction of radiation with matter may be measured at
21、 a given point by the use of a calibrated standard instrument. Dosimetry is the basis for the calibration of radiation protection instruments and devices and the determination of their response as a function of the energy of the radiation of interest. At present, the quantities in which photon secon
22、dary-standard instruments or sources are calibrated for use in radiological protection calibration laboratories relate to measurements made in free air, i.e.air kerma. NOTEThroughout this part of ISO4037, kerma is used as an abbreviation for air kerma. In order to correlate measured physical quantit
23、ies with the magnitude of a biological effect, a quantity of the dose equivalent type1 is required for use in radiation protection. ICRU has defined such quantities2 and a further International Standard will be issued containing tables of conversion coefficients from air kerma to these dose equivale
24、nt quantities (see ISO4037-3). 1 Scope This part of ISO4037 specifies the procedures for the dosimetry of X and gamma reference radiation for the calibration of radiation protection instruments over the energy range from approximately8keV to1,3MeV and from 4MeV to9MeV. The methods of production and
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