GB/T 12726.3-2013 Nuclear power plants—Instrunmentation important to safety—Radiation monitoring for accident and post-accident conditions—Part 3:Equipment for continous high range area gamma monitoring (English Version)
Nuclear power plants—Instrunmentation important to safety—Radiation monitoring for accident and post-accident conditions—Part 3:Equipment for continous high range area gamma monitoring
This part of GB/T 12726 specifies general guidance on the design principles and performance criteria for equipment for continuous high range area gamma monitoring in nuclear power plants for accident and post-accident conditions.
General requirements for technical characteristics, test procedures, radiation characteristics, electrical, mechanical, and environmental characteristics are given in GB/T 12726.1-2013. These requirements are applicable in this part unless otherwise stated.
This part is applicable to installed dose rate meters that are used to monitor high levels of gamma radiation during and after an accident. It covers equipment intended to isotropically measure air kerma, ambient dose or other exposure quantities due to gamma radiation of energy between 80 keV and 7 MeV. The equipment is intended primarily for the purpose of nuclear plant safety.
Portable instruments for emergency purposes and installed area radiation monitors used to determine continuously the radiological situation in working areas during normal operation are within the scope of GB/T 14054-2013.
2 Normative References
The following documents are indispensable for the application of this document. For dated references, only the dated editions apply. For undated references, the latest editions (including any amendments) apply.
GB/T 12726.1-2013 Nuclear Power Plants — Instrumentation Important to Safety — Radiation Monitoring for Accident and Post-accident Conditions — Part 1: General Requirements (IEC 60951-1:2009, IDT)
GB/T 14054-2013 (IEC 60532:2010, IDT)
ISO 4037 (all parts) X and Gamma Reference Radiation for Calibrating Dosemeters and Doserate Meters and for Determining Their Response As a Function of Photon Energy
ISO 6980 (all parts) Nuclear Energy — Reference Beta-particle Radiation
ISO 8529 (all parts) Reference Neutron Radiations
IEC 60780 Nuclear Power Plants — Electrical Equipment of the Safety System — Qualification
IEC 61226 Nuclear Power Plants — Instrumentation and Control Systems Important to Safety — Classification of Instrumentation and Control Functions
3 Terms and Definitions
For the purposes of this document, the terms and definitions given in GB/T 12726.1-2013 apply.
4 Design Principles
Foreword II Introduction IV 1 Scope 2 Normative References 3 Terms and Definitions 4 Design Principles 4.1 General 4.2 Range of measurement 4.3 Accuracy (relative error) 4.4 Location of sensors 4.5 Detector radiation response characteristics 4.6 Requirements related to accident conditions 5 Functional Testing 5.1 General 5.2 Reference sources 5.3 Performance characteristics Figure 1 Energy Response Table 1 Standards of SAC/TC 30/SC 2/SC 3 V Table 2 Additional Tests to Complement the General Tests Required in GB/T 12726.1-2013
GB/T 12726.3-2013 Nuclear power plants—Instrunmentation important to safety—Radiation monitoring for accident and post-accident conditions—Part 3:Equipment for continous high range area gamma monitoring (English Version)
Standard No.
GB/T 12726.3-2013
Status
valid
Language
English
File Format
PDF
Word Count
4000 words
Price(USD)
120.0
Implemented on
2014-8-1
Delivery
via email in 1~3 business day
Detail of GB/T 12726.3-2013
Standard No.
GB/T 12726.3-2013
English Name
Nuclear power plants—Instrunmentation important to safety—Radiation monitoring for accident and post-accident conditions—Part 3:Equipment for continous high range area gamma monitoring
1 Scope
This part of GB/T 12726 specifies general guidance on the design principles and performance criteria for equipment for continuous high range area gamma monitoring in nuclear power plants for accident and post-accident conditions.
General requirements for technical characteristics, test procedures, radiation characteristics, electrical, mechanical, and environmental characteristics are given in GB/T 12726.1-2013. These requirements are applicable in this part unless otherwise stated.
This part is applicable to installed dose rate meters that are used to monitor high levels of gamma radiation during and after an accident. It covers equipment intended to isotropically measure air kerma, ambient dose or other exposure quantities due to gamma radiation of energy between 80 keV and 7 MeV. The equipment is intended primarily for the purpose of nuclear plant safety.
Portable instruments for emergency purposes and installed area radiation monitors used to determine continuously the radiological situation in working areas during normal operation are within the scope of GB/T 14054-2013.
2 Normative References
The following documents are indispensable for the application of this document. For dated references, only the dated editions apply. For undated references, the latest editions (including any amendments) apply.
GB/T 12726.1-2013 Nuclear Power Plants — Instrumentation Important to Safety — Radiation Monitoring for Accident and Post-accident Conditions — Part 1: General Requirements (IEC 60951-1:2009, IDT)
GB/T 14054-2013 (IEC 60532:2010, IDT)
ISO 4037 (all parts) X and Gamma Reference Radiation for Calibrating Dosemeters and Doserate Meters and for Determining Their Response As a Function of Photon Energy
ISO 6980 (all parts) Nuclear Energy — Reference Beta-particle Radiation
ISO 8529 (all parts) Reference Neutron Radiations
IEC 60780 Nuclear Power Plants — Electrical Equipment of the Safety System — Qualification
IEC 61226 Nuclear Power Plants — Instrumentation and Control Systems Important to Safety — Classification of Instrumentation and Control Functions
3 Terms and Definitions
For the purposes of this document, the terms and definitions given in GB/T 12726.1-2013 apply.
4 Design Principles
Contents of GB/T 12726.3-2013
Foreword II
Introduction IV
1 Scope
2 Normative References
3 Terms and Definitions
4 Design Principles
4.1 General
4.2 Range of measurement
4.3 Accuracy (relative error)
4.4 Location of sensors
4.5 Detector radiation response characteristics
4.6 Requirements related to accident conditions
5 Functional Testing
5.1 General
5.2 Reference sources
5.3 Performance characteristics
Figure 1 Energy Response
Table 1 Standards of SAC/TC 30/SC 2/SC 3 V
Table 2 Additional Tests to Complement the General Tests Required in GB/T 12726.1-2013
