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GB/T 17982-2018 English PDF

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GB/T 17982-2018: Models and parameters for calculating radiation doses to the public in the emergency of a nuclear accident
Status: Valid

GB/T 17982: Evolution and historical versions

Standard ID	Contents [version]	USD	STEP2	[PDF] delivered in	Standard Title (Description)	Status	PDF
GB/T 17982-2018	English	579	Add to Cart	5 days [Need to translate]	Models and parameters for calculating radiation doses to the public in the emergency of a nuclear accident	Valid	GB/T 17982-2018
GB/T 17982-2000	English	719	Add to Cart	3 days [Need to translate]	Models and parameters for calculating radiation doses to the public in the event of a nuclear accident	Obsolete	GB/T 17982-2000

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Basic data

Standard ID	GB/T 17982-2018 (GB/T17982-2018)
Description (Translated English)	Models and parameters for calculating radiation doses to the public in the emergency of a nuclear accident
Sector / Industry	National Standard (Recommended)
Classification of Chinese Standard	C57
Classification of International Standard	13.280
Word Count Estimation	29,263
Date of Issue	2018-05-14
Date of Implementation	2018-12-01
Older Standard (superseded by this standard)	GB/T 17982-2000
Regulation (derived from)	National Standards Announcement No. 6 of 2018
Issuing agency(ies)	State Administration for Market Regulation, China National Standardization Administration

GB/T 17982-2018: Models and parameters for calculating radiation doses to the public in the emergency of a nuclear accident

---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order.
(Modes and parameters for estimating doses of public exposure to nuclear accident emergency situations) ICS 13.280 C57 National Standards of People's Republic of China Replace GB/T 17982-2000 Estimated public exposure dose in the event of a nuclear accident emergency Modes and parameters Published on.2018-05-14 2018-12-01 implementation State market supervision and administration China National Standardization Administration issued

Content

Foreword I 1 Scope 1 2 Terms and Definitions 1 3 Basic Principles 1 4 Early accident dose estimation 2 5 Mid-term dose estimation 5 6 Accidental dose prediction principle 7 Appendix A (informative) Radionuclides released during nuclear accidents that are important for the estimation of doses received by members of the public 8 Appendix B (informative) Important quantities required for model calculation or monitoring at different stages after an accident 10 Appendix C (informative appendix) plume irradiation pathway γ external irradiation dosimetry parameters 11 Appendix D (informative) Dosimetric parameters for radiation beta of radioactive inert gases in plumes Appendix E (informative) Skin dose conversion factor due to deposition of nuclide in the air or on the skin surface 13 Appendix F (informative) Inhaled radionuclide dosimetry parameters 14 Appendix G (informative) γ external irradiation dosimetry parameters caused by ground deposition nuclide 18 Appendix H (informative) Organization weight factor 20 Appendix I (informative) Ingestion radionuclide dosimetry parameters 21 Appendix J (informative) Dosimetric parameters for internal exposure doses from contaminated fresh foods 23 Appendix K (informative) Dosimetric parameters for internal exposure doses from contaminated “storage” foods 25 Reference 26

Foreword

This standard was drafted in accordance with the rules given in GB/T 1.1-2009. This standard replaces GB/T 17982-2000 "Personal exposure dose estimation mode and parameters in the case of nuclear accident emergency". Compared with GB/T 17982-2000, the main technical changes of this standard are as follows. --- Modified some terms and definitions; --- Modified some data of the relevant parameters in Table A.1, Table F.1, Table F.2, Table F.3, Table G.1, Table H.1, Table I.1, Table I.3 . This standard is proposed and managed by the National Health and Wellness Commission of the People's Republic of China. This standard was drafted. Radiation Protection and Nuclear Safety Medical Institute of China Center for Disease Control and Prevention, Radiation Medical Research, Chinese Academy of Medical Sciences Institute, Jiangsu Provincial Center for Disease Control and Prevention, Shenzhen Municipal Hospital for Occupational Diseases. The main drafters of this standard. Tuofei, Zhou Qiang, Zhang Qing, Yuan Long, Xu Cuihua, Zhang Liangan, Xu Xiaosan, Zhang Jing, Li Wenhong, Ma Jiayi, Wang Xiaoqiang, Zhang Jianfeng, Fu Ximing. The previous versions of the standards replaced by this standard are. ---GB/T 17982-2000. Estimated public exposure dose in the event of a nuclear accident emergency Modes and parameters

1 Scope

This standard proposes that the emergency radiation monitoring data (or the corresponding data derived from the plume diffusion model) be estimated at different stages of the nuclear accident emergency. Calculate the patterns and parameters of the public exposure dose. This standard applies to the estimation and evaluation of the radiation dose received by the public in the event of a nuclear accident emergency. The public is subject to normal operation of nuclear facilities The estimation and evaluation of the dose can also be referred to the application.

2 Terms and definitions

The following terms and definitions apply to this document. 2.1 Emergency emergency Some need to take immediate action beyond normal working procedures to avoid accidents or mitigate the consequences of accidents, sometimes referred to as Emergency; at the same time, it also refers to immediate action beyond normal working procedures. 2.2 Nuclear accident nuclearaccident A state of severe deviation from operational conditions in nuclear power plants or other nuclear facilities; in this state, the release of radioactive material The release may or may have lost the control it deserved to an unacceptable level. 2.3 Early accident early phaseofaccident From the aura of significant radioactive release (ie, the perceived consequences of off-site radiation) to the first few after the release The time of the hour. 2.4 Interim intermediatephaseofaccident The first few hours after the release of radioactive material has continued for a few days to a few weeks. At this stage, pass Most of the release has already occurred, and most of the radioactive material has been deposited on the ground, except when the inert gas is released. 2.5 Late phase accidentacicident It lasted for a few weeks to a few years since the middle of the accident. 2.6 Smoke plume plume An airborne "smoke cloud" of radioactive material released into the environment. 2.7 Resuspend resuspension The process of returning the pollutants from the surface of the ground, the surface of the object, etc., to the atmosphere due to the mechanical disturbance of the soil and the action of the wind.

3 basic principles

3.1 Estimating the exposure dose of members of the public in the event of a nuclear accident should take into account all major exposure routes and major radioactivity at different stages of the accident.

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