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HJ 842-2017 English PDF

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HJ 842-2017: Emergency-Related Parameters for Presurrized Water Reactor Nuclear Power Plants
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GB/T 4214.1   GB 1495   HJ 841   HJ 843   HJ 840   

Basic data

Standard ID HJ 842-2017 (HJ842-2017)
Description (Translated English) Emergency-Related Parameters for Presurrized Water Reactor Nuclear Power Plants
Sector / Industry Environmental Protection Industry Standard
Classification of Chinese Standard Z33
Word Count Estimation 49,471
Date of Issue 7/7/2017
Date of Implementation 8/1/2017
Issuing agency(ies) Ministry of Ecology and Environment

HJ 842-2017: Emergency-Related Parameters for Presurrized Water Reactor Nuclear Power Plants

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Emergency-Related Parameters for Presurrized Water Reactor Nuclear Power Plants National Environmental Protection Standard of the People 's Republic of China Relevant Parameters of PWR Nuclear Power Plant Emergency-Related Parameters For Presurrized Water Reactor Nuclear Power Plants 2017-7-7 release 2017-8-1 implementation Ministry of Environmental Protection released I directory

Foreword

1 Scope of application

2 normative reference documents

3 Terms and definitions 1 General 1 5 data content .2 Example of emergency related parameters Appendix A PWR nuclear power plant emergency related parameters (normative appendix) 4 Appendix BAP1000 Unit Emergency related parameters example (informative) Appendix C Example of Emergency Response Parameters for EPR Units (Informative Appendix) 18 Appendix D Example of Emergency Response Parameters for the M310 Unit (informative) .25 Appendix E VVER unit emergency related parameters example (informative) 32 Appendix F Examples of emergency response parameters for CNP300 units (informative) 39 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 People's Republic of China civilian nuclear facilities safety supervision and management regulations "to protect the environment, protect human health, regulate the PWR nuclear power plant Emergency related parameters, the development of this standard. This standard specifies the scope, content and format of the relevant parameters of PWR nuclear power plant. Appendix A of this standard is a normative appendix, Appendix B to F are informative appendices. 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, Suzhou Thermal Engineering Research Institute Co., Ltd. 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 PWR nuclear power plant emergency related parameters

1 Scope of application

This standard specifies the scope, content and format of the relevant parameters of the PWR nuclear power plant. This standard applies to the determination of the relevant parameters of the PWR nuclear power plant, and other heap type nuclear power plants may refer to the implementation.

2 normative reference documents

The 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 article Pieces. Design Safety Requirements for HAF 102 Nuclear Power Plant HAF 002/01 Emergency preparedness and emergency response of operating units in nuclear power plants HAD 002/01-2010 Emergency preparedness and emergency response to operating units of nuclear power plants

3 terms and definitions

The following terms and definitions apply to this standard. Emergency Emergency Need to take immediate action beyond the normal working procedures to avoid nuclear power plant nuclear accidents or mitigate accidents may occur The state of the consequences of life. Sometimes called a state of emergency. At the same time, it is also referred to immediately take the line beyond the normal working procedures move. 3.2 Emergency related parameters 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 General

4.1 Purpose In order to improve the national nuclear safety supervision departments of the nuclear power plant emergency supervision level, regulate the PWR nuclear power plant operating units to State - related safety regulatory authorities to provide emergency - related parameters. 4.2 Principles The emergency response parameters provided by the operating unit of the PWR nuclear power plant to the national nuclear safety supervision department should fully reflect the pressure The actual state of the nuclear power plant, the accident development process, the level of radiation and environmental impact, to meet the national nuclear safety regulatory authorities on the nuclear Requirements for Emergency Supervision and Management of Nuclear Accident in Power Plant. 4.3 Uses The emergency related parameters specified in this standard are mainly used for PWR nuclear power plant nuclear accident emergency, such as emergency state grading, heap Core damage assessment, accident consequences evaluation. 4.4 Classification According to the characteristics of the parameters with time and the source of the acquisition, the relevant parameters of PWR nuclear power plant are divided into design parameters, Real-time parameters and other measurement parameters. The design parameters in this standard refer to the static parameters that are determined by the PWR nuclear power plant and are related to the emergency, and the real- Is the dynamic parameter of the real-time monitoring related to the emergency during the operation of the PWR nuclear power plant. Other measurement parameters refer to the pressurized water reactor Dynamic parameters of non - real - time monitoring of emergency - related nuclear power plants during operation. 25 data content 5.1 Design parameters The important design parameters of PWR nuclear power plants include the following. Unit. Rated thermal power. Core. core stock, fuel component count, core thermal power, core active area height, core fuel average line power Rate, pressure vessel design temperature. One circuit. rated one-way coolant flow, reactor coolant system total volume, regulator safety valve opening pressure. Second circuit. two-circuit steam flow (rated power), steam generator water volume, steam generator outlet steam pressure (Rated power), steam maximum humidity (rated power), feed water temperature (rated power), evaporator safety valve opening pressure force. Containment. the inner diameter of the containment, the total volume of the containment, the free space in the containment, the design pressure of the containment On), containment design temperature, containment design leak rate. Picking system. high-pressure injection pump for the pump when the rated flow, high pressure injection when the maximum flow, low pressure injection rated flow the amount. See Appendix A, Table A.1 for the design parameters of PWR nuclear power plants. Appendix of the importance of marked "★" is required to be provided Of the parameters, the importance of the air can be based on the actual situation of PWR nuclear power plant free choice, the same below. 5.2 real-time parameters The real-time parameters of PWR nuclear power plants include the following. Unit. unit thermal power, unit nuclear power, unit power. Core. intermediate range neutron flux, source range neutron flux, emergency shutdown state, core outlet temperature, reactor cold Saturated margin. A loop. a boron concentration, reactor coolant system radioactive level, reactor coolant system pressure, reaction Reactor coolant system flow, regulator water level, regulator pressure relief valve opening, regulator safety valve opening. Second circuit. main feed water flow, steam flow, steam generator pressure, steam generator level (wide range), steam Generator level (narrow range), steam generator steam radioactive level, steam generator safety valve opening, steam generator Leakage rate, turbine side discharge valve opening, atmospheric release valve opening, condenser, radioactive level, condenser pressure. Nuclear auxiliary system. the capacity of the system on the flow, the capacity of the system discharge flow, the capacity of the system volume control box level, the main cold But the pump pump water flow, desalination tank water level, an important plant water flow. Containment. Containment pressure (wide range), containment pressure (narrow range), containment temperature, containment Air gamma radiation level, containment hydrogen concentration, containment isolation state, containment pit water level, containment pit water temperature, safety Full shell spray state, containment spray flow, refueling pool γ radiation level. Picking system. refueling tank water level, low pressure injection water flow, high pressure injection water flow (direct injection), high pressure injection Water flow (through the boron injection box), the injection section of the flow, the injection of cold section of the flow, the injection box water level, injection box pressure. Radioactivity control. Radiation level of the main control room, chimney effluent level (inert gas) (narrow range), chimney Effluent level (inert gas) (wide range). Spent fuel pool. spent fuel storage, spent fuel pool water level, spent fuel pool temperature, spent fuel plant radiation level. Radiation station. γ dose rate. Ground weather station. wind direction, wind speed. Factory Meteorological tower. wind direction, wind speed. Refer to Appendix A, Table A.2, for real-time parameters of PWR nuclear power plants. 5.3 Other measurement parameters Other important measurement parameters for PWR nuclear power plants include the following. 3 environmental monitoring. environmental gamma radiation air absorption dose rate, surface dose rate. Sampling monitoring. ground deposition nuclide activity concentration, air aerosol activity concentration, air iodine activity concentration, one back Road coolant 131I equivalent specific activity, total primary activity of a loop, and total air activity concentration in the containment. Refer to Appendix A, Table A.3 for additional measurement parameters for pressurized water reactor nuclear power plants.

6 Examples of emergency related parameters

Appendix B to F of this standard give an example of the emergency response parameters of a typical PWR nuclear power unit.

4 Appendix A

Relevant Parameters of PWR Nuclear Power Plant (Normative appendix) Table A.1 shows the design parameters provided by the operating unit of the PWR nuclear power plant to the national nuclear safety regulator. Table A.2 gives the The real-time parameters provided by the operating unit of the PWR nuclear power plant to the national nuclear safety supervision department, Table A.3 shows the pressurized water reactor nuclear power plant Other measurement parameters provided by the operating unit to the national nuclear safety regulator. Table A.1 Schematic tables of design parameters for PWR nuclear power plants System parameters Unit importance Remarks unit Rated thermal power MWth ★ In the case of rated power, the nuclear reactor reactor core release power and nuclear Steam supply system equipment, the sum of heat production Rated Output Electric Power MWe Unit Generator Output Power Core Core stock volume Bq ★ The nuclear power plant design report gives the balance of the cycle life at the end of the reactor The amount of radionuclide accumulated Number of fuel assemblies ★ Number of fuel assemblies in the core Core reactor thermal power MWth ★ nuclear reactor reactor core heat release power Fuel rods in a single fuel assembly Number of fuel components in the root fuel assembly Number of control rods in a single fuel assembly Number of control rods used to control the reactor in a fuel assembly Fuel assembly arrangement - Fuel rod arrangement in fuel assembly (eg 17 x 17) The first fuel cycle fuel uranium is rich Set degrees % Of the uranium enrichment of each zone at the first fuel cycle Balanced after the new fuel Uranium enrichment% Reactor balance cycle Newly loaded fuel rods Uranium enrichment Uranium loading total t reactor core loading fuel rod uranium quality Core active area height m ★ height of fuel assembly active area The equivalent diameter of the core is the diameter of the circle equal to the actual cross-sectional area of the reactor core Core power density kW/cm3 ratio of core release power to core volume Core fuel average power W/cm ★ core fuel rod unit length of the release power Core heat transfer area m2 Heat transfer area between core fuel rod and coolant Core average heat flux W/m2 core heat transfer power per unit area Fuel assembly Dimensions mm Fuel assembly Dimensions (length, width, height) Pressure vessel inner diameter mm Pressure vessel internal diameter Pressure vessel design pressure Correct) MPa Pressure vessel designed for maximum pressure (absolute) Pressure vessel design temperature ℃ ★ Normally, the temperature of the metal cross section of the set pressure vessel is flat Mean Refueling period Nuclear power plant in the normal operation of the situation between the two shut down refueling time interval Fuel center peak temperature ℃ fuel rod pellet center temperature maximum value one time Rated one-way coolant flow rate kg/s ★ Rated torrent of each reactor coolant system coolant loop flow The amount of design value Reactor coolant pressure MPa rated power reactor coolant system main pipe pressure design value Rated power loop cold section temperature ℃ Nuclear power plant rated power when running, reactor coolant system cold section Tube coolant temperature design value Rated power loop hot temperature ℃ Nuclear power plant rated power when running, reactor coolant system hot section Tube coolant temperature design value Rated power loop average temperature ℃ Nuclear power plant rated power when running, cold section temperature and hot section temperature average value 5 Table A.1 Design table for pressurized water reactor nuclear power plant (continued) System parameters Unit importance Remarks one time Total volume of reactor coolant system m³ ★ Total load of coolant in reactor coolant system Reactor coolant system design pressure Force (absolute) MPa reactor coolant system designed to withstand the pressure (absolute) Reactor coolant system design temperature ℃ Temperature of the metal cross section of the reactor coolant system Main coolant pump shaft seal water injection amount m³/h The main coolant pump is used during the operation of the water for the mechanical seal Rate of entry Voltage regulator design temperature ℃ The regulator can withstand the maximum temperature along the regulator section Regulator Design Pressure MPa Voltage regulator designed for maximum pressure (absolute) Number of regulators' safety valves - Number of safety valves in the upper part of the regulator Regulator safety valve opening pressure MPa ★ trigger regulator safety valve to open the design pressure The electric heater power is supplied by the electric heater within the voltage regulator Only the heating rate of the electric heater is C/h Only the electric heater of the regulator operates so that the reactor coolant system rises Temperature, the unit time the temperature rise Regulator rated capacity when steam capacity M³ Nuclear power plant rated load operation, the gas volume within the regulator The rated capacity of the regulator when the water volume m³ nuclear power plant rated load operation, the regulator liquid volume Regulator continuous spray flow L/h When the top of the regulator is connected to the cooling piping unit of the cold pipe The amount of coolant provided in the room Regulator auxiliary spray flow m³/h The top of the regulator is connected to the chemical and volumetric control system for regenerative heat transfer The downstream of the device on the line of the spray line, the unit time The volume of coolant provided Main coolant pump head MPa main coolant pump inlet and outlet pressure difference Main coolant pump design temperature ℃ Main coolant pump designed to withstand temperature values Main coolant pump design pressure MPa main coolant pump designed to withstand pressure values Main coolant pump rated power kW Under rated current and pressure head, the main coolant pump motor power Main coolant pump Moment of inertia kg · m2 Main coolant pump flywheel inertia inertia value Main coolant pump design flow m3/h main coolant pump design unit time driven coolant volume Two times back Two-circuit steam flow (rated power) rate) Kg/s ★ rated power, steam generator steam flow design value Steam generator water capacity kg ★ rated power, the steam generator water capacity Steam generator outlet steam pressure (rated power) MPa rated power, steam generator pressure design value Steam maximum humidity (rated work rate) % ★ rated power, steam generator secondary side steam quality Steam temperature (rated power) ℃ rated power, the steam generator secondary side of the steam temperature Feed water temperature (rated power) ℃ ★ rated power, the steam generator secondary side of the feed water temperature Steam generator shell side design pressure MPa steam generator secondary side of the design to withstand pressure Evaporator safety valve opening pressure MPa ★ steam generator safety valve opening pressure design value Auxiliary water supply tank capacity m³ Auxiliary water supply tank can store the volume of coolant Number of auxiliary feed pumps The number of auxiliary feed pumps in the auxiliary water supply system Safety Containment inner diameter m ★ containment internal diameter Thickness of containment wall Total volume of containment m³ ★ Containment internal volume Free space inside the containment chamber m³ ★ total volume inside the containment device to remove the equipment after the space Containment design pressure (absolute) MPa ★ containment design to withstand the pressure (absolute) Containment design temperature ℃ ★ containment designed to withstand the temperature Safe shell design Leakage rate%/d ★ Enclosure design allows the amount of daily leakage 6 Table A.1 Design parameters of pressurized water reactor nuclear power plant (continued) System parameters Unit importance Remarks fuel And put it Radioactive control Spent fuel storage capacity A spent fuel pool can store the number of fuel components Number of Evaporators for Evaporation of Radioactive Waste Waste storage tank decay tank quantity Nuclear power plant waste treatment system can be used to store decay radioactive waste The number of decay tanks Waste storage Decay tank capacity m³ Nuclear power plant waste treatment system can be used to store decay radioactive waste Liquid decay tank volume Exhaust gas storage decay tank quantity Nuclear power plant waste treatment system can be used to store decay radioactive waste The number of decay tanks Exhaust gas storage decay tank capacity m³ Nuclear power plant waste treatment system can be used to store decay radioactive waste Gas decay tank volume Liquid effluent discharge monitoring alarm Threshold Bq/m³ On - line radiation monitoring system for radioactive liquid effluent discharge pipeline Alarm threshold Chimney effluent monitoring alarm threshold (Aerosol) Alarm threshold for aerosol monitoring of Bq/m3 chimney exhaust Chimney effluent monitoring alarm threshold (iodine) Bq/m3 chimney exhaust for iodine monitoring channel alarm threshold Chimney effluent monitoring alarm threshold (Inert gas) Alarm threshold for inert gas monitoring of Bq/m3 chimney exhaust Liquid tritium emission limits Bq National liquidation regulations approved by the national nuclear safety authorities Liquid 14C normal discharge limit Bq national nuclear safety regulatory authorities approved liquid 14C emission limits Liquid radioactive effluent Tritium, 14C) emission limits Bq National nuclear safety regulatory authorities approved the liquid radioactive effluent Except for 3H, 14C other than the nuclide emission limits Inert gas emission limits Bq National air safety regulatory authorities approved inert gas emission limits Gaseous Tritium Discharge Limit Bq National GH Fire Regulatory Authority Approves Gaseous 3H Emission Limits Gaseous 14C emission limits Bq Gaseous 14C emission limits approved by national nuclear safety regulators Gaseous radioactive effluent (not included Tritium, 14C) emission limits Bq National nuclear safety regulatory authorities approved the release of aerosols and halogens Limit Ann system The number of high - pressure injection pump design of the number of high - pressure injection pump Maximum inlet pressure during high pressure installation MPa High pressure injection, high pressure injection pump inlet maximum pressure High-pressure installation when the maximum inlet temperature ℃ high-pressure injection, the high-pressure injection pump inlet maximum temperature High pressure injection pump for the charge pump time Constant flow M³/h ★ high-pressure injection pump to make the pump when the rated flow rate Maximum flow during high pressure installation m³/h ★ high pressure injection unit time can provide the amount of coolant Low - pressure injection pump number of low - pressure injection pump design number Low-pressure installation when the maximum inlet pressure MPa for low-pressure injection, the low-pressure injection pump inlet maximum pressure Low-pressure installation when the maximum inlet temperature ℃ for low-voltage injection, the low-pressure injection pump inlet maximum temperature Low pressure installation rated flow m³/h ★ low pressure injection unit time can provide the amount of coolant The number of the number of cases The capacity of the coolant can be stored Injection box design pressure MPa working pressure of the injection box Burst box...

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