IEEE N323D-2002
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
American National Standard for Installed Radiation Protection Instrumentation
14-11-2024
31-12-2003
1 Scope
2 Definitions
3 General requirements
3.1 Operational characteristics
3.2 Acceptance
3.3 Performance tests
3.4 Routine function tests
3.5 Source response check
3.6 Enhanced capabilities
3.7 Special use conditions
3.8 Instrument repair
4 Calibration
4.1 Pre-calibration
4.2 Calibration
4.3 Discrimination against interfering radiations
4.4 Detector geometry dependence
4.5 Detector interchangeability
5 Calibration equipment
5.1 Calibration standards
5.2 Calibration assemblies
6 Calibration quality
6.1 Calibration facility
6.2 Calibration frequency
6.3 Records
Annex A (informative) - Automated contamination instruments
Annex B (informative) - Bibliography
Establishes specific requirements for installed instruments that measure dose, dose equivalent, dose rate, or dose equivalent rate and for installed instruments used to detect and/or measure the presence of radioactive contamination.
Committee |
Gyro Accelerometer Panel
|
DocumentType |
Standard
|
PublisherName |
Institute of Electrical & Electronics Engineers
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Status |
Withdrawn
|
IEEE/ANSI N323AB-2013 | American National Standard for Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments |
IEC 60050-394:2007 | International Electrotechnical Vocabulary (IEV) - Part 394: Nuclear instrumentation - Instruments, systems, equipment and detectors |
IEEE/ANSI N323A-1997 | American National Standard Radiation Protection Instrumentation Test and Calibration, Portable Survey Instruments |
IEC 61098:2003 | Radiation protection instrumentation - Installed personnel surface contamination monitoring assemblies |
ISO 6980:1996 | Reference beta radiations for calibrating dosemeters and dose-rate meters and for determining their response as a function of beta-radiation energy |
ISO 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 ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV |
ISO 10647:1996 | Procedures for calibrating and determining the response of neutron-measuring devices used for radiation protection purposes |
ANSI N1.1 : 1976 | NUCLEAR SAFETY - CRITICAL EXPERIMENTS, SAFETY GUIDE FOR THE PERFORMANCE OF |
ISO 8529:1989 | Neutron reference radiations for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy |
ISO 8769-2:1996 | Reference sources for the calibration of surface contamination monitors Part 2: Electrons of energy less than 0,15 MeV and photons of energy less than 1,5 MeV |
ISO 4037-1:1996 | X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Part 1: Radiation characteristics and production methods |
ANSI N13.6 : 2010 | PRACTICE FOR OCCUPATIONAL RADIATION EXPOSURE RECORDS SYSTEMS |
ISO 8769:2016 | Reference sources Calibration of surface contamination monitors Alpha-, beta- and photon emitters |
ISO 4037-3:1999 | X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence |
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