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Basic dataStandard ID: HJ 844-2017 (HJ844-2017)Description (Translated English): Emergency-Related Parameters for Nuclear Fuel Cycle Facilities Sector / Industry: Environmental Protection Industry Standard Classification of Chinese Standard: Z33 Word Count Estimation: 20,215 Date of Issue: 7/7/2017 Date of Implementation: 8/1/2017 Issuing agency(ies): Ministry of Ecology and Environment HJ 844-2017: Emergency-Related Parameters for Nuclear Fuel Cycle Facilities---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.Emergency-Related Parameters for Nuclear Fuel Cycle Facilities National Environmental Protection Standard of the People 's Republic of China Nuclear fuel cycle facilities emergency related parameters 2017-7-7 release 2017-8-1 implementation Ministry of Environmental Protection released I directory Preface I 1 Scope of application2 normative reference documents3 Terms and definitions 1 General 1 5 data content .2 6 typical accident .4 Appendix A Design Guidelines for Nuclear Fuel Cycle Facilities (Normative Appendix) Appendix B Real-time parameters for nuclear fuel cycle facilities (normative) 10 Appendix C Nuclear fuel cycle facilities Other measurement parameters (normative) Appendix D Nuclear Fuel Cycle Facilities Typical Accident (Informative Appendix) .. 16 I preface For the implementation of the "People's Republic of China Environmental Protection Law" "People's Republic of China Radioactive Pollution Prevention Law" and "China Regulations of the People's Republic of China on the Safety Supervision and Management of Civil Nuclear Facilities, Protecting the Environment, Ensuring Human Health and Regulating Nuclear Fuel Circulation Emergency response parameters, the development of this standard. This standard specifies the scope, content, and format of the relevant parameters of the nuclear fuel cycle facility emergency response. Appendix A to Appendix C of this standard are normative and Appendix D is an informative appendix. This standard is organized by the Ministry of Environmental Protection Nuclear Safety Management Division, Science and Technology Standards Division. The main drafting of this standard. the Ministry of Environmental Protection Nuclear and Radiation Safety Center, China Nuclear Power Engineering Co., Ltd. Zhengzhou Branch Division. The environmental protection department of this standard approved on July 7,.2017. This standard has been implemented since August 1,.2017. This standard is explained by the Ministry of Environmental Protection.1 nuclear fuel cycle facilities emergency related parameters1 Scope of applicationThis standard specifies the scope, content, and format of the relevant parameters of the nuclear fuel cycle facility emergency response. This standard applies to civilian nuclear fuel recycling facilities, including uranium conversion facilities, centrifugal separation facilities, pressurized water reactor nuclear combustion Material manufacturing facilities, spent fuel reprocessing facilities.2 normative reference documentsThe following documents are indispensable for the application of this document. Note the date of the reference file, only the date of the date of the note Apply to this document. For undated references, the latest edition (including all modifications) applies to this document. Regulations on Safety Supervision and Management of Civil Nuclear Facilities Regulations on Emergency Management of Nuclear Accidents in HAF002 Nuclear Power Plant Safety Requirements for Civil Nuclear Fuel Recycling Facilities Emergency Preparedness and Emergency Response of Nuclear Fuel Recycling Facility Operating Units3 terms and definitionsThe following terms and definitions apply to this standard. Emergency Emergency Need to take some action immediately beyond the normal working procedures to avoid accidents or mitigate the consequences of the accident. Have Also known as a state of emergency. 3.2 Emergency-related parameters Emergency-related parameter Nuclear accident emergency preparedness and response to the need to use the parameters, emergency related parameters can be divided into design parameters, real-time parameters and its He measured the parameters.4 General4.1 Purpose In order to improve the level of emergency supervision of nuclear fuel recycling facilities by national nuclear safety regulators, regulate nuclear fuel cycle facilities The relevant parameters provided by the operating unit to the national nuclear safety supervision department. 4.2 Principles The emergency response parameters provided by the nuclear fuel cycle facility to the national nuclear safety regulator should be sufficient The actual state of the nuclear fuel cycle facilities, the accident development process, the level of radiation and environmental impact, to meet the national nuclear safety supervision Requirements for emergency supervision and management of nuclear accident in nuclear fuel cycle facilities. 4.3 Uses The emergency related parameters specified in this standard are mainly used for nuclear fuel cycle facilities nuclear accident emergency, such as emergency status grading, Accident consequences evaluation. 4.4 Classification According to the characteristics of parameters change with time and the source of access, the relevant parameters of nuclear fuel cycle facilities are divided into design parameters, Real-time parameters and other measurement parameters. In this standard, the design parameters refer to the static parameters, real-time parameters that have been identified by the nuclear fuel cycle facility and are related to the emergency Refers to the dynamic parameters of real-time monitoring of emergency-related nuclear fuel cycle facilities during operation, and other measurement parameters refer to The dynamic parameters of non-real-time monitoring of emergency-related nuclear fuel cycle facilities during operation. 25 data content 5.1 Design parameters 5.1.1 uranium conversion facility Uranium conversion facility Important design parameters include the following. UF4 conversion system. a fluidized bed design temperature, two fluidized bed design temperature. UF6 conversion system. fluorination reactor design temperature. Condensing liquefaction system. a condenser condensing design temperature, a condenser liquefaction design temperature, a condenser design Loading capacity, secondary condenser condensation design temperature, secondary condenser liquefaction design temperature, secondary condenser design loading capacity, three Class condenser Condensation design temperature, three-stage condenser liquefaction design temperature, three-stage condenser design loading, 3m3 container loading the amount. Safety monitoring system. HF concentration alarm set value, hydrogen leak alarm set value. See Appendix A for the design parameters of the nuclear fuel cycle facility. Appendix of the importance of marked "★" is the need to provide the Senate Number, the importance of empty can be based on the actual situation of nuclear fuel recycling facilities free choice, the same below. 5.1.2 Centrifugal separation facility Centrifugal separation facilities Important design parameters include the following. Discharge system. discharge tank design pressure, freezing device design temperature. Feeding system. heating box design temperature. Concentrate feed system. cold box design temperature, take the container design loading capacity. Poor material reclaiming system. cold box design temperature, take the container design loading capacity, hot and cold wind box condensation design temperature, hot and cold Bellows liquefaction design temperature. Liquefaction homogenization system. pressure tank design temperature, safety box design pressure, by the material container design loading capacity. Safety monitoring system. HF concentration alarm set value, critical accident alarm system setting value. 5.1.3 PWR nuclear fuel manufacturing facilities PWS Nuclear Fuel Manufacturing Facility Important design parameters include the following. Dry chemical conversion system. gasification tank design temperature, converter design pressure. Wet chemical conversion system. gasification tank design temperature, ADU drying design temperature, defluorination reduction furnace design pressure. Pellet preparation system. sintering furnace design pressure. Safety monitoring system. HF concentration alarm set value, hydrogen leakage alarm set value, leak detection tank conductivity alarm set value, Leakage tank acidity alarm set value, critical accident alarm system setting value. 5.1.4 spent fuel reprocessing facilities Spent fuel reprocessing facilities Important design parameters include the following. Spent fuel receiving storage. pool surface γ radiation level control value, storage pool water temperature design value. Element Shear and Material Preparation. Solvent Temperature, Solvent Level Design Value. Uranium nitrate conversion product packaging and tetravalent uranium preparation. evaporator design temperature. Plutonium purification cycle. 2AX column -2BX column -2BS column neutron count rate control value, high concentration plutonium storage tank hydrogen concentration. Plutonium nitrate conversion and product packaging. Plutonium quality in plutonium phosphate pellet reactor, Neutral counting rate control of plutonium oxalate precipitation reactor Value. High level, put waste liquid treatment. evaporator heating saturated steam design pressure. 1AW high-level waste liquid storage. tank hydrogen concentration, tank waste liquid temperature. Safety monitoring system. critical accident alarm system setting value, process equipment pressure control value, equipment room/hot chamber pressure control Value, orange zone pressure control value. 35.2 Real-time parameters 5.2.1 uranium conversion facility Important real-time parameters for uranium conversion facilities include the following. See Appendix B for real-time parameters of nuclear fuel cycle facilities. UF4 conversion system. a fluidized bed temperature, two fluidized bed temperature. UF6 conversion system. fluorination reactor temperature. Condensing liquefaction system. a condenser temperature, a condenser charge capacity, two condenser temperature, two condenser installed Material, three-stage condenser temperature, three-stage condenser charge, 3m3 container loading. Radioactivity control. Emission activity of airborne effluent. Safety monitoring system. HF concentration, hydrogen concentration, fire alarm signal. Ground weather station. wind direction, wind speed. 5.2.2 Centrifugal separation facility The important real-time parameters of the centrifugal separation facility include the following. Discharge system. unloading tank pressure, freezing device temperature. Feeding system. heating box temperature. Material reclaiming system. cold box temperature, take the amount of container loading. Poor material reclaiming system. cold box temperature, take the container loading, hot and cold air box temperature. Liquefaction homogenization system. the internal temperature of the pressure tank, the temperature of the cold box, the capacity of the container charge. Radioactivity control. Emission activity of airborne effluent. Safety monitoring system. HF concentration, critical accident gamma radiation level, fire alarm signal. Ground weather station. wind direction, wind speed. 5.2.3 PWR nuclear fuel manufacturing facilities Compressor heap nuclear fuel manufacturing facilities Important real-time parameters include the following. Dry chemical conversion system. gasification tank temperature, converter pressure. Wet chemical conversion system. gasification tank temperature, ADU drying temperature, defluorination reduction furnace pressure. Pellet preparation system. sintering furnace pressure. Radioactivity control. Emission activity of airborne effluent. Safety monitoring system. HF concentration, hydrogen concentration, conductivity, acidity value, critical accident gamma radiation level, fire alarm signal. Ground weather station. wind direction, wind speed. 5.2.4 spent fuel reprocessing facilities Excessive real-time parameters for spent fuel reprocessing facilities include the following. Spent fuel to receive storage. pool surface γ radiation level, storage pool water temperature. Element Shear and Liquid Preparation. Solvent Temperature, Dissolver Level. Uranium nitrate conversion product packaging and tetravalent uranium preparation. evaporator temperature. Plutonium purification cycle. neutron counting rate, hydrogen concentration. Plutonium nitrate conversion and product packaging. plutonium quality, neutron counting rate. High release, put waste liquid treatment. evaporator heating saturated steam pressure. 1AW high-level waste liquid storage. tank hydrogen concentration, tank waste liquid temperature. Radioactivity control. Emission activity of airborne effluent. Safety monitoring system. critical accident γ radiation level, fire alarm signal, process equipment pressure, equipment room/hot room pressure, Orange zone pressure. Ground weather station. wind direction, wind speed. 45.3 Other measurement parameters 5.3.1 uranium conversion facility, centrifugal separation facility, PWR nuclear fuel manufacturing facility Uranium conversion facilities, centrifugal separation facilities, pressurized water reactor nuclear fuel manufacturing facilities Other important measurement parameters include the following. Environmental monitoring. ambient gamma radiation air absorption dose rate. 5.3.2 spent fuel reprocessing facilities The other measurement parameters that are important for spent fuel reprocessing facilities include the following. Sampling monitoring. concentration of radionuclide activity in spent fuel pool, concentration of radionuclide activity in high level radioactive waste. Environmental monitoring. ambient gamma radiation air absorption dose rate. Nuclear Fuel Cycle Facility See Appendix C for other measurement parameters.6 typical accidentThe typical cause of the nuclear fuel cycle facility considered in this standard in determining the relevant emergency parameters is given in Annex D.5 Appendix ADesign parameters of nuclear fuel cycle facilities (Normative appendix) Table A.1 shows the design parameters provided by the Uranium Conversion Facility operating unit to the national nuclear safety regulator. Table A.2 shows the design parameters The design parameters provided by the centrifugal separation facility operating unit to the national nuclear safety regulatory authority, Table A.3 shows the PWR The design parameters provided by the facility to the national nuclear safety regulator, Table A.4 shows the operation of the spent fuel reprocessing facility The design parameters provided by the unit to the national nuclear safety supervision department. Table A.1 Description of uranium conversion facility design parameters System parameters Unit importance Remarks Facility production capacity tU/a annual production capacity by uranium UF4 conversion system First - class fluidized bed design temperature ℃ ★ Consider the material corrosion and ensure the UF4 conversion rate conditions Under the first class of fluidized bed design temperature Two - stage fluidized bed design temperature Consider the material corrosion and ensure the UF4 conversion rate conditions Under the design temperature of the secondary fluidized bed HF intake design flow rate Nm3/h to meet the fluidized bed UF4 conversion rate of HF inlet flow The amount of HF in the fluidized bed exhaust gas is the minimum excess of the fluidized bed conversion rate UF6 conversion system Fluorination reactor design temperature ℃ ★ Taking into account material corrosion and ensuring UF6 conversion conditions , The design temperature of the fluorination reactor F2 intake design flow rate Nm3/h Fluoride reactor UF6 conversion rate of F2 into the air flow Condensation liquefaction system Class 1 Condenser Condensation Design Temperature ℃ ★ In the condensation, ensure that UF6 gas to achieve the design of condensation efficiency temperature First-class condenser liquefaction design temperature ℃ ★ in liquefaction, to prevent UF6 liquefaction overpressure temperature Class 1 Condenser Design Pressure MPa Condenser Contains UF6 Gas Design Pressure Class 1 Condenser Design Charge Quantity kg ★ Maximum allowable charge in the condenser Secondary Condenser Condensation Design Temperature ℃ ★ In the condensation, ensure that UF6 gas to achieve the design of condensation efficiency temperature Secondary condenser liquefaction design temperature ℃ ★ to ensure the safe transfer of UF6 gas temperature Secondary Condenser Design Pressure MPa Contains UF6 Gas Design Pressure Secondary Condenser Design Charge Quantity kg ★ Maximum allowable charge in the condenser Three - stage condenser condensation design temperature ℃ ★ In the condensation, ensure that UF6 gas to achieve the design of condensation efficiency temperature Three-stage condenser liquefaction design temperature ℃ ★ to ensure the safe transfer of UF6 gas temperature Condensation liquefaction system Three-stage condenser design pressure MPa inclusive UF6 gas design pressure Class 3 Condenser Design Charge Quantity kg ★ Maximum allowable charge in the condenser 3m3 container loading kg ★ 3m3 the maximum allowable loading capacity in the container Carbon reactor jacket temperature ℃ to meet the safe requirements of the safe operation of the temperature F2 production system The temperature of the electrolytic cell is designed to meet the safe operation temperature of the electrolyzer The design pressure of the electrolytic cell Pa satisfies the safe operation of the electrolyzer The electrolytic cell design level m meets the level of safe operation of the electrolyzer HF system HF tank design effective volume m3 HF storage tank designed storage capacity HF Evaporative Tank Design Pressure MPa HF Evaporator Safe Pressure HF Evaporative Tank Design Temperature ℃ HF Evaporator Safe Operating Temperature Radioactive control Emission limit for radioactive airborne effluent Bq/a Emission control value approved by national nuclear safety regulatory authority Radiation liquid effluent emission limits Bq/a Emission control values approved by national nuclear safety regulatory authorities Safety monitoring system HF concentration alarm set value mg/m3 ★ occurred HF, F2, UF6 leakage alarm value Hydrogen leak alarm set value% ★ occurrence of hydrogen leakage alarm value Note. the importance of marked "★" is the need to provide the parameters, the importance of the empty can be based on nuclear fuel recycling facilities The situation is free to choose the same. 6 Table A.2 Centrifugal separation facility design parameter specification table System parameters Unit importance Remarks Facility separation capacity tSWU/a year separation capacity in tons Centrifugal cascade system Feeding pipe pressure Pa To ensure that the cascade process system safe operation of the supply pipe pressure range Concentrate outlet pressure Pa To ensure that the cascade process system safe operation of the concentrate export pressure range Discharge system Unloading tank design pressure Pa In the case of centrifugal cascade operation, ensure that the cascade will be single The material in the meta-system is pumped to the specified pressure in the unloading tank Freezer design temperature ℃ ★ ensure that UF6 gas to achieve the design of the condensing efficiency of the temperature Zero line Zero tank design pressure Pa Stable zero gauge system with specified pressure Supply system heating box design temperature ℃ ★ in liquefaction, to prevent UF6 liquefaction overpressure design temperature Concentrate material system Cold bellows design temperature ℃ ★ In......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of HJ 844-2017_English be delivered?Answer: Upon your order, we will start to translate HJ 844-2017_English as soon as possible, and keep you informed of the progress. 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