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HJ 843-2017 English PDF

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HJ 843-2017: Emergency-Related Parameters for Research Reactors
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Basic data

Standard ID HJ 843-2017 (HJ843-2017)
Description (Translated English) Emergency-Related Parameters for Research Reactors
Sector / Industry Environmental Protection Industry Standard
Classification of Chinese Standard Z33
Word Count Estimation 27,242
Date of Issue 7/7/2017
Date of Implementation 8/1/2017
Issuing agency(ies) Ministry of Ecology and Environment

HJ 843-2017: Emergency-Related Parameters for Research Reactors

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Emergency-Related Parameters for Research Reactors National Environmental Protection Standard of the People 's Republic of China Relevant parameters of research reactor 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

6 Example of emergency response parameters for research reactors

Appendix A Relevant parameters of the reactor (normative) 4 Appendix B Tsinghua University Nuclear Energy Technology Design and Research Institute 10MW high temperature air-cooled reactor (HTR-10) emergency related parameters (Informative) .10 Appendix C China Atomic Energy Research Institute China Experimental Fast Reactor (CEFR) Emergency related parameters (informative) 17 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, standard research reactor emergency phase Off the standard, the development of this standard. This standard specifies the scope, content and format of the relevant parameters of the reactor. Appendix A to this standard is a normative appendix, Appendix B, Appendix C 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. Nuclear and Radiation Safety Center of the Ministry of Environmental Protection, China Nuclear Power Research and Design Institute. 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 Relevant parameters of the reactor

1 Scope of application

This standard specifies the scope, content and format of the relevant parameters of the reactor. This standard applies to nuclear reactors that produce and utilize neutron fluence rates and ionizing radiation for research or other purposes, Including low-throughput research reactors, high-throughput research reactors, pulsed reactors, and material test reactors.

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 of HAF201 research reactor HAF202 research reactor operation safety regulations HAF001/02/02 Regulations of the People's Republic of China on the Supervision and Administration of Civil Nuclear Facilities Regulations II. Unit reporting system HAD002/06 research reactor contingency plan and preparation

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 accidents or mitigate the consequences of the accident. Also known as the state of emergency; at the same time, also refers to immediately take action beyond the normal working procedures. 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 regulatory authorities on the level of emergency monitoring of the research reactor, regulate the research reactor operating units to the national nuclear Safety regulators provide emergency related parameters. 4.2 Principles The emergency response parameters provided by the research reactor operating unit to the national nuclear safety supervision department should fully reflect the research reactor Actual state, accident development process, radiation level and environmental impact, to meet the national nuclear safety regulatory authorities on the research reactor nuclear emergency Supervision and management requirements. 4.3 Uses The emergency-related parameters specified in this standard are mainly used to study the reactor nuclear emergency, such as emergency grading, core damage assessment Price, accident consequences evaluation. 4.4 Classification According to the characteristics of the parameters with time and the source of the study, the relevant parameters of the research reactor are divided into design parameters, Number and other measurement parameters of the three categories. 2 In this standard, the design parameters refer to the static parameters that the research reactor has identified and is related to the emergency; the real- The dynamic parameters related to the real-time monitoring related to the emergency during the operation; other measurement parameters refer to the research reactor during the operation Dynamic parameters related to emergency non-real-time monitoring.

5 data content

5.1 Design parameters The important design parameters of the research reactor include the following. Fuel components. shape, material, maximum line power, maximum fuel temperature, fuel element surface maximum temperature. Core. fuel number, 235U capacity, rated thermal power, rated nuclear power, maximum neutron fluence rate, average neutron fluence Rate, fuel element breakage rate, core coolant flow rate, core inlet coolant temperature, core outlet coolant temperature. Reactor container. coolant level, design pressure, design temperature. One circuit system. coolant type, coolant charge, coolant flow rate, coolant leak rate, coolant inlet temperature Degree, coolant outlet temperature. Residual heat exhaust system. one circuit coolant inlet flow, one circuit coolant inlet temperature, one circuit coolant outlet temperature degree. Second circuit system. working medium type, working medium capacity, working medium flow, working medium leakage rate. Heat exchanger. primary working medium inlet flow, primary working medium outlet temperature, secondary side working medium inlet Flow, secondary side working medium inlet temperature, secondary side working medium outlet flow, secondary side working medium outlet temperature. A loop system inclusion body. net space volume, design pressure, design temperature, design leakage rate. Spent fuel storage facilities. spent fuel storage capacity, design temperature. Exhaust gas storage facilities. quantity, exhaust gas storage, design pressure, design temperature. Waste storage facilities. quantity, waste storage, design pressure, design temperature. Radioactivity control. nuclear radionuclide stock, radionuclide activity in a loop coolant, spent fuel Radioactivity. See Appendix A, Table A.1 for the design of the study reactor. Appendix of the importance of "★" is the need to provide the parameters, The degree of importance is empty according to the actual situation of the research reactor free choice, the same below. 5.2 real-time parameters The important real-time parameters of the research reactor include the following. Core. core power, thermal power, power doubling cycle, neutron fluence rate, core outlet coolant temperature. Reactor container. Reactor container coolant level, reactor vessel pressure. One-way cooling system. one-way coolant flow rate, one-way coolant leak rate. Residual heat exhaust system. one circuit coolant inlet flow, one circuit coolant inlet temperature, one circuit coolant outlet temperature degree. Heat exchanger. primary working medium inlet flow, primary working medium outlet temperature, secondary side working medium inlet Flow, secondary side working medium inlet temperature, secondary side working medium outlet flow, secondary side working medium outlet temperature. A circuit system inclusion body. pressure, temperature. Spent fuel storage facilities. temperature. Radioactivity control. the concentration of radionuclide activity in the process flow, the total β activity concentration between the processes, the total γ activity concentration between the processes, Inter-process iodine activity concentration, inter-process aerosol activity concentration, inter-process gamma dose rate, chimney effluent inert gas activity concentration Degree, chimney discharge current iodine activity concentration, chimney effluent flow aerosol activity concentration. Ground weather station. wind direction, wind speed. Refer to Appendix A, Table A.2 for the real-time parameter description of the research reactor. 5.3 Other measurement parameters Other measurement parameters important to the research reactor include the following. 3 sampling monitoring. chimney effluent radionuclide activity concentration, radioactive waste effluent flow nuclide activity concentration. Environmental monitoring. ambient gamma radiation air absorption dose rate. Refer to Appendix A, Table A.3 for additional measurement parameters.

6 Examples of research reactor emergency related parameters

Appendix B, C of this standard gives examples of typical research reactor emergency related parameters.

4 Appendix A

Relevant parameters of research reactor (Normative appendix) Table A.1 gives the design parameters provided by the research reactor operating units to the national nuclear safety regulatory authorities. Table A.2 gives the study The real-time parameters provided by the operating units to the national nuclear safety regulator are shown in Table A.3. The operating units of the research reactor are given to the national nuclear Other measurement parameters provided by safety regulators. Table A.1 Description of the design parameters of the study reactor System parameters Unit importance Remarks fuel element Shape - ★ the geometry of the fuel element (rod, ball, plate, etc.) Material - ★ fuel components (core, cladding, cladding, etc.) Size mm The size of the fuel element corresponding to the fuel element geometry (Diameter, length, width, thickness, etc.) Maximum line power kW/m ★ Maximum fission power per unit length Fuel maximum temperature ℃ ★ fuel core temperature safety limits Maximum temperature of fuel element surface ℃ ★ Fuel element surface temperature safety limits The fuel contained in each box of fuel Number of components The total number of fuel elements contained in a unit of the core (For fuel assemblies) Core Shape - the geometry of the core (cylinder, cone, etc.) Size mm The size of the equivalent core corresponding to the core geometry (straight Diameter, height, etc.) Volume m3 core active area volume Number of fuel A unit (fuel element, fuel assembly) that is loaded into the core Etc.) the total number UO2 capacity kg The total mass of UO2 in the new fuel 235U capacity kg ★ new fuel in the total quality of 235U 235U enrichment% 235U of new fuel in the total quality of the total share of uranium Rated thermal power MWth ★ The energy and system of fission in unit time Produce heat plus Rated nuclear power MW ★ rated operating conditions, the amount of energy per unit time fission Rated electrical power MWe rated power, the unit time output power Maximum power density MW/m3 Maximum fission power per unit volume Average power density MW/m3 Average of fission power per unit volume Maximum neutron fluence rate n/(cm2 · s) ★ unit time per unit area of the largest neutron number (sub-energy group) Average neutron fluence rate n/(cm2 · s) ★ unit time per unit area of the average neutron number (sub-energy group) Fuel consumption range MWd/t Unloading the minimum and maximum fuel consumption of a single spent fuel element in the core Large value Fuel component breakage% ★ Damaged fuel components account for the total share of core fuel components Core coolant flow rate kg/s ★ coolant flow through the core Core inlet coolant temperature ℃ ★ Core inlet coolant average temperature Core outlet coolant temperature ℃ ★ core outlet coolant average temperature reaction Pile up shape- The geometry of the container (pressure vessel, pool, etc.) containing the core shape Size mm A reactor vessel corresponding to the geometry of the reactor vessel Size (diameter, height, etc.) Coolant Level mm ★ Level of coolant in the reactor vessel Design pressure MPa ★ Pressure vessel designed for maximum pressure Design temperature ℃ ★ Under normal circumstances, set the temperature of the pressure vessel metal cross section average value Table A.1 Description of the design parameters of the research reactor (continued)

5 System parameters Unit importance Remarks

one time Road system Coolant type - ★ such as water, sodium, helium and so on Coolant Charge kg ★ Total amount of coolant in a circuit system Coolant flow rate kg/s ★ Total flow of coolant in a circuit system Coolant leakage rate m3/d ★ a circuit system coolant design reference leakage rate Coolant pressure MPa Working temperature of the circuit system coolant Coolant inlet temperature ℃ ★ a circuit coolant into the core temperature Coolant outlet temperature ℃ ★ a circuit coolant out of the core temperature Waste heat discharge system One circuit coolant inlet flow rate kg/s ★ return flow of coolant into the waste heat exhaust system inlet One-way coolant inlet pressure MPa One-way coolant flows into the inlet of the waste heat exhaust system One circuit coolant outlet pressure MPa one circuit coolant out of the heat removal system at the outlet pressure A circuit coolant inlet temperature ℃ ★ a circuit coolant into the waste heat discharge system inlet temperature A circuit coolant outlet temperature ℃ ★ a circuit coolant out of the waste heat exhaust system outlet temperature Two times back Road system Working medium type - ★ such as water, steam, sodium and so on Working medium loading kg ★ Total amount of working medium in secondary circuit system Working medium flow kg/s ★ Total flow of working medium in the secondary circuit system Working medium leakage rate m3/d ★ two circuit system working medium design reference leakage rate Working medium design pressure MPa Secondary circuit working medium in the secondary circuit system within the average pressure Working medium design temperature ℃ secondary circuit working medium in the secondary circuit system average temperature Heat Replacement Primary working medium inlet flow kg/s ★ flow of primary working medium into the heat exchanger inlet Primary working medium inlet pressure MPa Primary side of the working medium into the heat exchanger inlet pressure Primary working medium Outlet pressure MPa Primary side of the working medium Outflow of heat exchanger outlet pressure Primary working medium inlet temperature ° C Primary side of the working medium Flow temperature at the inlet of the heat exchanger Primary working medium outlet temperature ℃ ★ a working medium out of the heat exchanger outlet temperature Secondary side working medium inlet flow kg/s ★ secondary side of the medium into the heat exchanger inlet flow Secondary side working medium inlet pressure MPa secondary side of the water into the heat exchanger inlet pressure Secondary side working medium inlet temperature ℃ ★ secondary side of the water into the heat exchanger inlet temperature Secondary side working medium outlet flow kg/s ★ secondary side of the steam out of the heat exchanger outlet flow Secondary side working medium outlet pressure MPa secondary side steam outflow pressure at outlet of heat exchanger Secondary side working medium outlet temperature ℃ ★ secondary side of the steam out of the heat exchanger outlet temperature one time Road system Unified package Capacity Total volume m3 The total volume of the system body Net space volume m3 ★ remove the inclusion of all the facilities and equipment free space volume Design pressure MPa ★ normal operation and accident conditions can withstand the maximum pressure Design temperature ℃ ★ normal operation and accident conditions can withstand the maximum temperature Design leakage rate Nm3/h ★ normal operation and accident conditions can withstand the maximum leakage rate Exhausted Material storage Deposit Spent fuel storage capacity ★ a storage facility can store up to the number of fuel components Sub - criticality - sub - criticality expressed by keff Design temperature ℃ ★ Under normal operating conditions, the temperature of the storage facility Exhaust gas Storage facility Quantity ★ storage of radioactive waste gas storage facilities (storage tanks, etc.) the number Exhaust gas storage m3 ★ The maximum volume of radioactive waste that can be stored in each storage facility Design pressure MPa ★ Maximum pressure that each storage facility can withstand Design temperature ℃ ★ Maximum temperature that each storage facility can withstand Waste liquid Storage facility Quantity of radioactive waste storage facilities (storage tanks, etc.) the number Waste storage m3 m3 The maximum volume of radioactive waste that can be stored in each storage facility Design pressure MPa ★ Maximum pressure that each storage facility can withstand Design temperature ℃ ★ Maximum temperature that each storage facility can withstand Table A.1 Description of the design parameters of the research reactor (continued)

6 System parameters Unit importance Remarks

radiation Sex control Core radioactive nuclide stock Bq ★ core radionuclide activity A radioactive core in a coolant Activity concentration Bq/L ★ Radiation radionuclide specific activity in a circuit coolant Spent Fuel Radioactivity Bq ★ Spontaneous fuel radionuclide activity for maximum fuel consumption Emission limits for radioactive airborne effluents Bq/a National nuclear safety regulatory authorities approved the radioactive airborne effluent Emission limits Emission limits for radioactive liquid effluents Bq/a National nuclear safety regulatory authorities approved the radioactive liquid effluent Emission limits Note. the importance of "★" is the need to provide the parameters, the importance of the empty according to the actual situation of the research reactor free Choose the same. 7 Table A.2 Real-time parameter description tables for research reactors System parameters Unit importance Remarks Core Nuclear power% ★ Nuclear power monitoring channel monitoring value (rated power share) Thermal power MWth ★ Thermal power monitoring channel monitoring value Power doubling cycle s ★ Power cycle monitoring channel monitoring value Neutron fluence rate n/(cm2 · s) ★ neutron fluence monitoring channel monitoring value Core outlet coolant temperature ℃ ★ core outlet coolant monitoring channel monitoring value reaction Pile up Reactor container coolant level Heap container level monitoring channel monitoring value (for liquid cooling Agent) Reactor container pressure MPa ★ Heap container pressure monitoring channel monitoring value (for sealing capacity) Device) one time Cold road But the system One circuit coolant flow rate kg/s ★ one circuit coolant flow monitoring channel monitoring value One circuit coolant leakage rate kg/s ★ one circuit coolant leak monitoring channel monitoring value Waste heat discharge system One circuit coolant inlet flow rate kg/s ★ waste heat discharge system flow monitoring channel monitoring value A circuit coolant inlet pressure MPa residual heat discharge system pressure monitoring channel monitoring value One circuit coolant outlet pressure MPa residual heat discharge system pressure monitoring channel monitoring value A circuit coolant inlet temperature ℃ ★ waste heat discharge system temperature monitoring channel monitoring value A circuit coolant outlet temperature ℃ ★ waste heat discharge system temperature monitoring channel monitoring value Heat Replacement Primary working medium inlet flow kg/s ★ Heat exchanger primary working medium inlet flow monitoring channel monitoring Measured value Primary working medium outlet temperature ℃ ★ Heat exchanger primary working medium outlet temperature monitoring channel monitoring Measured value Secondary side working medium inlet flow kg/s ★ Heat exchanger secondary side working medium inlet flow monitoring channel monitoring Measured value Secondary side working medium inlet temperature ℃ ★ Heat exchanger secondary side working medium inlet temperature monitoring channel monitoring Measured value Secondary side of the working medium export flow kg/s ★ Heat exchanger secondary side working medium outlet flow monitoring channel monitoring Measured value Secondary side working medium outlet temperature ℃ ★ Heat exchanger secondary side working medium outlet temperature monitoring channel monitoring Measured value one time Road system Unified package Capacity Pressure ℃ ★ contain the body air pressure monitoring channel monitoring value Temperature MPa ★ Contains the body air temperature monitoring channel monitoring value Exhausted Material storage Deposit Temperature ℃ ★ spent fuel storage facilities temperature monitoring channel monitoring value radiation Sex control The total activity of the process flow Bq/L Process flow (a circuit coolant, two-loop working medium, etc.) Total alpha radioactive monitoring channel monitoring values or sampling laboratory measurements Total concentration of process flow β activity Bq/L Process flow (a circuit coolant, two-loop working medium, etc.) Total beta radioactivity monitoring channel monitoring values or sampling laboratory measurements The total activity of the total flow conc...

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