GB/T 15146.11-2004 Nuclear criticality safety of fissile materials outside reactors Nuclear criticality safety based on confinement and control of moderators
Some standard content:
S 27.120.30
National Standard of the People's Republic of China
GB/T15146.11—2004
Nuclear criticality safety for fissile materials outside the reactor Nuclear criticality safety based on confinement and control of moderators Issued on 2004-05-27
General Administration of Quality Supervision, Inspection and Quarantine of the People's Republic of China Standardization Administration of China
Implementation on 2004-12-01
Normative documents
5 Terms and definitions
Rules for implementation of nuclear criticality safety
5 Implementation plan for the control area projectwwW.bzxz.Net
Appendix A (Informative Appendix)||t t||Appendix (Informative Appendix)
Appendix (Informative Appendix)
Appendix D (Informative Appendix)
Classic Moderator Materials
Potential Chemistry Sources
Measurement of Chemical Properties of Moderators
Measurement of Barriers to Moderators
GB/T15146.11—2004
GB/T15146.11—2004
Youxu Stack The 3 safety regulations for the safe handling of fissile materials have been implemented by engineers and fissile material experts. The nuclear safety requirements for the safe handling of fissile materials have been met by customers during storage, transportation, and operation. Criticality safety can be achieved by limiting the number of fissile materials such as geometry, quality, and distance. In addition, the number of fissile materials that are safely handled, stored, or processed, and the range of slowing down the process, according to the definition, is the key to the successful completion of the chemical reaction. The critical air volume of fissile materials should be small. Therefore, by controlling the moderator (i.e. controlling the moderator within a certain period of time), the allowable amount of fissile materials that is significantly lower than the allowable amount of moderators can be considered as suitable for screening:
This part provides a wide range of requirements for achieving nuclear clinical safety by limiting and controlling the moderator within the range of no moderation to the best performance.
This part is one of the series of standards for the safety of fissile materials in the environment of criticality. Nuclear safety standards for fissile materials in the reactor! The following 10 parts have been issued, with the specific names as follows: B15146.1 General safety standards for magnetic criticality safety of fissile materials outside reactors; B15141.2 Basic technical standards and values for operation, processing and treatment of fissile materials outside reactors:
(H15146. Nuclear criticality safety of fissile materials outside reactors - Nuclear criticality safety requirements for fissile materials GB15146.4 Nuclear criticality safety of fissile materials outside reactors - Nuclear safety standards for the transfer of temporary materials and subcritical materials:
(Zhan 1546.3 Nuclear safety standards for fissile materials - Nuclear equipment and subcriticality control standards Limitation: GB/T1516.6 Nuclear safety of reactive materials - Silicate glass inserts and their application criteria (GB/T1511, 7 Safety regulations for in-situ measurements of fissile materials in reactors 3! GB1514. Safety regulations for the connection, storage and transportation of light water reactor materials. The requirements for the performance of nuclear criticality detection and warning systems for fissile materials. GB1514.3 Nuclear criticality safety of reactive materials - Safety requirements for fixed neutron collectors 3, this part meets the requirements of ASI/ANg, 221S9?\Nclaar critealr safe-y bsed an lminR The basic contents of this part are the same as those of ANSL/AS·19. Appendix A, Appendix 1, Appendix C and Appendix 1 of this part are the appendixes for the preparation of nuclear energy standards. This part is issued by the National Nuclear Energy Standardization Technical Committee and is under the jurisdiction of the National Nuclear Energy Standardization Technical Committee. The originating unit of this part is the Nuclear Industry Standardization Research Institute. The main drafter of this part is Yang Renhai.
-Fan Tian
Nuclear criticality safety of fissile materials outside the reactor Nuclear criticality safety based on limiting and controlling the explosive agent GB/T:5146.11—2004
This standard specifies the method of ensuring the critical safety of fissile materials by limiting and controlling the moderator in the moderator control zone.
It is applicable to achieve the critical safety of fissile materials by limiting and controlling the moderator in the moderator control zone. 2 Normative references
The provisions in the following documents are used as references to this standard and are the referenced documents that may be used. All subsequent revisions (excluding errors or revised versions) are not applicable to this standard. However, all parties who have reached an agreement based on this standard before publication shall verify whether the new version of these documents refers to the new version. For referenced documents without annotated dates, the latest version applies to technical standards. 115146.1 Reactor external fissile materials. For nuclear criticality safety, nuclear criticality safety management list, established GB1514C.2 Reactor external fissile materials, criticality safety, fissile materials, frequency conversion, and processing Basic technical principles and critical limits
EJ/1071 Nuclear safety training guidelines
3 Technical activities and definitions
This part allows the use of the following terms and definitions:
Moderator
The process by which neutrons are reduced in energy by continuous reduction without significant capture by moderator atoms 3.2
Moderator
Material that can be significantly reduced in energy by increasing the energy of the moderator. 3.3
Moderator control area moderatorcontrolarea The area defined by the conditions in which chemical changes are limited to ensure nuclear safety. 3.4
Moderator control engineered barrier moderatoratpreuntrolengineered burricr A specially designed tangible physical system used to limit or control the introduction of moderator atoms to ensure nuclear safety. \3.5
Process evaluation
refers to the document that defines and agrees on all items involved in nuclear safety, including the design, requirements, compensation and control of nuclear criticality safety, and the verification of subcriticality management. Process evaluation is often referred to as critical safety evaluation (CE). 4
Main principles of critical safety implementation
4.1 Administrative implementation rules for moderator limitation and control 1: In the attached document, typical experience of moderators is required. 2) In the attached document, typical safety tests of moderator control are listed: B/1 15146.11-204
4..1 A schedule should be prepared, and the process should also include the emergency safety limits and differential measures of the work. This procedure 1 clearly defines the steps to be taken when the moderator is under control:
4.1.2 A written sequence of testing, test frequency and maintenance should be provided to ensure that the results and controls determined in the evaluation are maintained. 4.1.3 The list of moderators and the analysis required by the evaluation should be provided. 4.1.4 According to the provisions of the special provisions, the workpiece personnel should be marked in the work area. 4.1.5 Other measures should be posted to limit the average value of the moderator control. 4.1.6 The fire control plan should include the requirements for the addition of moderator control. 4.1, in the control of moderators, it should be practiced to the minimum. 2.1.6 For the nuclear gas anomaly, the relevant personnel shall conduct relevant training on understanding and implementing the moderator control and control. In 1/1074, more guidance can be obtained. 4.1. For the relevant administrative management instructions, see GB15146.1. 4.2 Evaluation of moderator limit and control
4.2.1 Determine the moderator control area during the process. 4.2.2 During the independent evaluation period, the vehicle is operating normally and there is no reliable film. Under normal conditions, all operations are in a subcritical state. 4.2.3 The evaluation should clarify the limit values of the moderator control area to improve the process. In order to compensate for the experimental data,! The process evaluation should include all material properties of the moderator, such as moisture absorption, oxygen content, absorption, absorption, and transmission of new components. 4.2.5 The process evaluation should include all existing, introduced, or accumulated (not discussed, still released) moderators in the process control.6 The process evaluation should indicate the distribution of the moderator within the fissile material and within each fissile material unit. It should also indicate the distribution of the moderator that may have occurred during the mechanical (thermal) or chemical process. 4.2.7 The process evaluation should indicate the changes in the moderator's chemical and physical properties. 4.2.8 The process evaluation should indicate the presence of inappropriate activity in the transfer, storage, or moderator preparation area. ||t 2.2.9 The evaluation shall identify the types of slow-moving chemicals that may occur during maintenance, repair, construction and operation activities. 4.2.1 The evaluation shall identify the needs for special fire prevention and fire control measures, and shall consider the impact of fire control activities in the immediate area. 5.2. The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 4.2.12 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.13 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.14 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.15 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.16 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.17 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.18 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.19 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.20 The evaluation shall identify the types of chemical products that may be used during maintenance, repair, construction and operation activities. 5.2.21 Chemical control area. Engineering implementation rules
5.1 Slow down control area barrier
According to the evaluation requirements, the slow down control area should be virtually set up! The process group should be in good condition, "the integrity of the chemical control barrier should be achieved with all processes and the chemical control barrier should be guaranteed to fall outside the risk.
5.2 Equipment and customer reliability
The quality of materials and processes used in the chemical control area should be designed, manufactured and maintained. In order to ensure the safety of the chemical control area, the chemical control barrier should be designed and maintained according to the evaluation requirements. Agent.
5.3 Penetrations
5.3.1 The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. The sound will penetrate the control area and the thickness of the control area. 5.3.3 Systems that pass through the slowing agent control area but do not contain a chemical agent (ventilation ducts, compressed air ducts, air guides, and non-release pipes) should have the control measures required by the process evaluation. 5.4 Fire prevention and fire fighting
5.4.1 The control measures for hazards in the slowing agent control area should include the design features of the room indicated in the process evaluation. The use of the chemical agent as a medium should be considered:
5.4.2 The fuel should be ignited rather than combustible. 5.4.3 In the control of the retardant, the combustible materials should be minimized. The retardant sweeping materials introduced by the fire extinguishing activities should be reduced. The necessary combustible materials or non-flame retardant materials should be combined to minimize the damage of the rapid fire. 5.5 Instruments and control devices can be used to measure or prevent the release of igniters: Instruments and control devices in the evaluation of the requirements should be: All requirements of our field are required for design, installation, operation and management. CB/T15146.11-2004
Appendix 4
(Informative Appendix)
Typical Moderator Materials
Many materials commonly used in control may be moderators: among them, some materials may be more effective than water in moderation. The following materials (completed) are helpful for the examination of materials that may leak moderators: - Alcohol:
Hydrogen or other hydroxide radicals:
Anti-you liquid:
-Organic village materials
Carbon such as non-plastic, charcoal>;
Fiberboard,
Cleaning agent:
A very condensing 1:
Building materials:
Vapor compounds:
Annular combustion or atmospheric ventilation:
Fire village materials:
Fuel pellets adhesive and pore-forming agent:
-Vapor sleeves, kerosene!
Pressure fluid;
Chemical compounds!
Hydrocarbons and other organic materials;
-Slip agents:
Animal:
Paint!
Paper and paper products:
stone,
pre-halogenated parts:
human body,
materials (wearing devices and boards, etc.),
tree stock, esters, etc.:
polyethylene
paste storage;
secret fragrance:
heart tissue can also provide more human emotional environment.
7) Human resources have a greater ability to chemically modify, 4
Raw materials;
-blurring agent
sponge;
stabilizer,
-water·
home sand or three rows:
technical head and point to the product.
GB/T 15146, 11—2C04
C8/T15146.11—2004
Attachment H
【Information List】
Potential moderator sources
In addition to the listed materials that have not been removed from the nuclear power plant: these materials will not be introduced through the design, they will also be introduced intentionally through the following paths listed. The following categories and equipment systems are (incompletely) helpful for the operation of only the possible sources of chemical action. B.1 Plant pipelines: water pipelines, water pipes; roof drainage lines: running water ridge lines; H.2 Pipes and pipes associated with variable rate operations; pipelines: ventilation pipes: gas pipelines: heating and cooling systems. H.3 Equipment: three-way distribution and smoke control systems: heating and cooling lines.
High efficiency filter:
Novoben filter!
Lubrication system:
Integrated safety discharge gastric exchange voucher.
B.4 Construction materials
Sealant:
Epoxy resin,
Repair and reconstruction activities
R.6 Decontamination materials
Disinfection,
City and paper technology;
— Foaming materials.
B.7 Environment
-Moisture in the atmosphere
-Rain,
-Water film,
Process chemicals or source additives
Binders or pore-forming agents;
-"Feed liquid flow:
-Road agents:
Slowdown caused by process softness.
H.9 Accident and emergency response
Fire extinguishing Water pipeline:
—Fire extinguishing software:
-"-water use,
Class A fire extinguisher
B.13 person-caused interference
Fire extinguishing by the full introduction of the chemical;
Unauthorized introduction of the chemical;
One digging cloth request;
One person point person:
CB/T15146.11—2004
GB/T 15146.11—2004
Appendix ℃
(Informative Appendix)
Measurement of Moderator Content
The following contents are intended to ensure the integrity of the measurement and process. C.1 An appropriate plan should also be followed according to the following: C.1.1 Concepts and steps to be noted during sample preparation and analysis C.1.2 Operation and maintenance requirements of measurement equipment C.1.3 Instrument configuration requirements.
C1.4 Data requirements.
C.2 Take six methods to provide various representative analysis samples. In the process of sampling and analysis, ensure the integrity of the sample. C.3 Study the separation of at least two samples obtained for each sampling station analysis. The lowest is that when reliability is based on a single analysis method, the plan should use independent instrumentation to analyze the products. C.4 Various independent moderator measurements should be consistent with the existing confidence level. C.5 Produce appropriate standards to verify that the analysis method meets the requirements of the feasible process. C.6 Use the standards to prove that the system is qualified after maintenance. And, evaluate the entire standard regularly before or after the same or more sets of plans.
C.7 Determine the various requirements for control using standards. CB proves that the various analysis methods are qualified by determining that the offset, uncertainty and detection limits of the quality and quantity moderator are at the specified confidence level.
C.9 Using the continuous over-weakness monitoring card method, it can be proved that the transformation produced by the process system is indeed within the required moderator opening limit value. o
Appendix D
(Informative Appendix)
An example of controlling moderator engineering failure
Engineering screen can be used as a method to prevent moderator introduction. Typical screens include the following: double-entry: auxiliary ceiling panels; one-effect enhancement: steam screens: push-button interface, normally closed windows, sealed devices, one-point suction circuit breakers: reflux devices, condensation collectors; one-way blocking and troubleshooting (suction) devices: various containers: various equipment for attenuation: equipment (air dryers) and instrumentation and control systems (need to be equipped with indicators, neutron detectors). GB/T15146.11—20D4
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