CN109543941A - A method of nuclear power plant's accident strategy definite value is determined based on containment operating condition - Google Patents

A method of nuclear power plant's accident strategy definite value is determined based on containment operating condition Download PDF

Info

Publication number
CN109543941A
CN109543941A CN201811196532.1A CN201811196532A CN109543941A CN 109543941 A CN109543941 A CN 109543941A CN 201811196532 A CN201811196532 A CN 201811196532A CN 109543941 A CN109543941 A CN 109543941A
Authority
CN
China
Prior art keywords
definite value
operating condition
accident
error
instrument
Prior art date
Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
Granted
Application number
CN201811196532.1A
Other languages
Chinese (zh)
Other versions
CN109543941B (en
Inventor
易珂
杜宇
司天琪
李力
孙涛
赵侠
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN201811196532.1A priority Critical patent/CN109543941B/en
Publication of CN109543941A publication Critical patent/CN109543941A/en
Application granted granted Critical
Publication of CN109543941B publication Critical patent/CN109543941B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06QINFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
    • G06Q10/00Administration; Management
    • G06Q10/06Resources, workflows, human or project management; Enterprise or organisation planning; Enterprise or organisation modelling
    • G06Q10/063Operations research, analysis or management
    • G06Q10/0639Performance analysis of employees; Performance analysis of enterprise or organisation operations
    • G06Q10/06395Quality analysis or management
    • GPHYSICS
    • G06COMPUTING; CALCULATING OR COUNTING
    • G06QINFORMATION AND COMMUNICATION TECHNOLOGY [ICT] SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES; SYSTEMS OR METHODS SPECIALLY ADAPTED FOR ADMINISTRATIVE, COMMERCIAL, FINANCIAL, MANAGERIAL OR SUPERVISORY PURPOSES, NOT OTHERWISE PROVIDED FOR
    • G06Q50/00Information and communication technology [ICT] specially adapted for implementation of business processes of specific business sectors, e.g. utilities or tourism
    • G06Q50/06Energy or water supply

Landscapes

  • Business, Economics & Management (AREA)
  • Human Resources & Organizations (AREA)
  • Engineering & Computer Science (AREA)
  • Economics (AREA)
  • Strategic Management (AREA)
  • Theoretical Computer Science (AREA)
  • Entrepreneurship & Innovation (AREA)
  • Educational Administration (AREA)
  • Marketing (AREA)
  • Development Economics (AREA)
  • Health & Medical Sciences (AREA)
  • Tourism & Hospitality (AREA)
  • Physics & Mathematics (AREA)
  • General Business, Economics & Management (AREA)
  • General Physics & Mathematics (AREA)
  • Public Health (AREA)
  • Primary Health Care (AREA)
  • Water Supply & Treatment (AREA)
  • General Health & Medical Sciences (AREA)
  • Game Theory and Decision Science (AREA)
  • Operations Research (AREA)
  • Quality & Reliability (AREA)
  • Testing And Monitoring For Control Systems (AREA)

Abstract

The invention belongs to nuclear safety assessment technique fields, are related to a kind of method for determining nuclear power plant's accident strategy definite value based on containment operating condition.Described method includes following steps: (1) determining the parameter definite value nominal value in accident treatment strategy;(2) judge and screen the crucial definite value of accident treatment strategy;(3) instrument error of crucial definite value under containment nominal situation and unfavorable operating condition is determined;(4) influence of the analysis meter error to accident treatment directive/guide;(5) definite value accordance analytical calculation is verified;(6) it verifies and confirms.Utilize a kind of method that nuclear power plant's accident strategy definite value is determined based on containment operating condition of the invention, instrument error under the operating condition can be considered respectively for different containment operating conditions (nominal situation and unfavorable operating condition), and influence of the instrument error to definite value crucial in accident strategy is combined to optimize calculating, obtain two groups of definite values under nominal situation and unfavorable operating condition.Judge that can the definite value meet criterion calls finally by verifying is calculated.

Description

A method of nuclear power plant's accident strategy definite value is determined based on containment operating condition
Technical field
The invention belongs to nuclear safety assessment technique fields, are related to one kind based on containment operating condition and determine nuclear power plant's accident strategy The method of definite value.
Background technique
Nuclear power plant system is complicated, and there are many operating parameter, once there are accident conditions, is considered as nuclear power plant into urgent shape State requires operator to make rapid reaction at this time, corrects operating condition and deviates, and takes necessary action possible to avoid or mitigate Consequence.Accident treatment code is to realize the important component of nuclear power plant's depth defense, it is directly related to the operation of nuclear power plant Safety develops to limitation accident and guarantees that the safety of reactor plays an important role.
Accident treatment strategy can be used to alleviate and limit damage sequence.The definite value being applied in accident treatment strategy can For executing the diagnosis of accident, damage sequence can be alleviated by manual operation according to the definite value of setting, and definite value can be passed through Confirmation nuclear power plant is in safe shutdown operating condition.Therefore correct setting definite value is extremely important.In the design process of definite value, at accident The operating condition for managing strategy must include the environmental condition of containment high temperature and pressure height irradiation, instrument under the conditions of this unfavorable work condition environment Watch Error often deteriorates.And in order to guarantee the validity of accident key parameter definite value, it needs to consider instrument error in definite value Setting in, the instrument error under the especially above-mentioned unfavorable working condition of containment.Therefore, it is necessary to be based on difference to crucial definite value Containment operating condition analyzed, consider that the instrument error under containment nominal situation and unfavorable operating condition influences, to tactful definite value Carry out reasonability optimization.
Summary of the invention
The object of the present invention is to provide a kind of method for determining nuclear power plant's accident strategy definite value based on containment operating condition, the party Method can determine the definite value in accident strategy respectively in connection with instrument error, and calculate and test in containment normally and under unfavorable operating condition Demonstrate,prove whether the definite value meets criterion calls.
In order to achieve this, the present invention provides one kind and determines nuclear power based on containment operating condition in the embodiment on basis The method of factory's accident strategy definite value, the method include the following steps:
(1) the parameter definite value nominal value in accident treatment strategy is determined;
(2) judge and filter out the crucial definite value of accident treatment strategy;
(3) instrument error of crucial definite value under containment nominal situation and unfavorable operating condition is determined;
(4) influence of the instrument error to accident treatment directive/guide under containment nominal situation and unfavorable operating condition is analyzed, according to Need to modify tactful crucial definite value;
(5) verifying of definite value accordance analytical calculation is carried out;
(6) it is verified and is confirmed by design verification platform.
The present invention is based on the definite value in accident treatment strategy, wherein crucial definite value is filtered out, and combine instrument in containment Instrument error under normal and unfavorable operating condition analyzes influence of the operating condition to accident treatment strategy, it is ensured that parameter definite value it is effective Property and determine by meeting analytical calculation the acceptable degree of instrument error, carried out finally by means such as verification platforms comprehensive Policy validation, confirm the correctness and availability of accident treatment strategy and definite value.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value, wherein in step (1), based on the analysis to accident treatment strategy, to being completed in its step for task or Corresponding definite value is arranged in person's function, and is calculated by accordance and carry out efficiency analysis to the definite value of setting, ultimately forms a set of complete Whole accident treatment strategy, and confirm definite value nominal value therein.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value wherein in step (2), judges and filters out the crucial definite value for needing to consider instrument error in accident treatment strategy And the influence that instrument error generates under containment nominal situation and unfavorable operating condition is analyzed to such definite value.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value, wherein the screening technique of step (2) include:
1) it is used for accident diagnosis, determines the trend of accident treatment strategy;
2) judged by definite value, need to execute security function by manual measure to slow down damage sequence;
3) for judging the effect of accident mitigation.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value, wherein in step (3), based on unit design feature and crash analysis conclusion determine containment nominal situation with And unfavorable operating condition boundary, the instrument that crucial definite value in accident treatment strategy is calculated and determined under nominal situation and unfavorable operating condition are always missed Difference.
In a kind of more preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident based on containment operating condition The method of tactful definite value, wherein in step (3), the instrument overall error should miss instrument and the precision of channel all components Difference counts, including instrument measurement directional error, isolation module error, I/O fastener module error and display instrument are missed Difference.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value, wherein in step (4):
On the one hand, the influence by the unfavorable operating condition of containment to crucial definite value is needed to take into account, if being considered always definite value Instrument error under nominal situation, it will cause measurement result inaccurate, be unable to envelope and live under the unfavorable operating condition of containment to occur greatly The case where error;
On the other hand, it is also necessary to avoid the influence that instrument error under unfavorable operating condition is excessively considered in design process.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value, wherein in step (5), for modified definite value, firstly, carrying out accordance analytical calculation by calculation procedure The acceptable degree of crucial definite value and instrument error in accident treatment strategy is verified, if calculated result cannot after verifying It meets the requirements, at this moment the error of instrument has influenced the execution of accident treatment strategy, then needs to reselect instrument and carry out again Analysis and calculating.After calculating instrument error, the crucial definite value in accident treatment strategy is verified by accordance analytical calculation And the acceptable degree of instrument error, if cannot meet the requirements after verifying, the error of instrument has influenced accident treatment plan Execution slightly, then need to reselect instrument and analyzed and verified again.
In a preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident strategy based on containment operating condition The method of definite value wherein in step (6), finally by design verification platform, carries out comprehensively dynamically testing for accident treatment strategy Card and confirmation, confirm the reasonability of directive/guide strategy and definite value, if cannot meet the requirements after verifying, need to re-start instrument Analysis and verifying.
In a kind of more preferred embodiment, the present invention provides one kind and determines nuclear power plant's accident based on containment operating condition The method of tactful definite value, wherein in step (6), the reasonability of the uncertainty definite value includes whether personnel's intervention time fills It is abundant.
The beneficial effects of the present invention are determine nuclear power plant's accident strategy definite value based on containment operating condition using of the invention Method, can containment normally and unfavorable operating condition under, determine the definite value in accident strategy respectively in connection with instrument error, can The safety margin for guaranteeing directive/guide definite value under the unfavorable operating condition of containment, will not make containment nominal situation definite value excessively consider instrument The influence of error.Calculating the verifying directive/guide strategy and definite value by accordance analytical calculation and design verification platform can satisfy Design requirement.
Beneficial effects of the present invention are embodied in:
(1) the present invention is based on the comprehensive analysis to accident treatment strategy, in conjunction with instrument containment is normal and unfavorable work Error under condition has carried out the uncertainty to accident treatment strategy definite value for containment nominal situation and unfavorable operating condition respectively Impact analysis, and the analysis for proposing a kind of PWR nuclear power plant accident treatment strategy definite value containment operating condition uncertainty determines Method can be respectively set for different containment operating conditions (such as normal and unfavorable operating condition) by this method and consider containment operating condition The accident directive/guide strategy definite value of uncertainty, and ensure the validity of parameter definite value by simulating calculating or verification experimental verification.This The methodology of invention is applicable to the design of pressurized-water reactor nuclear power plant unit failure processing strategie definite value.
(2) the invention proposes a kind of methods of crucial definite value for screening accident treatment strategy.
(3) present invention employs accordance analytical calculation and double authentication policies of verification platform, to guarantee nuclear power plant's thing Therefore important parameter definite value validity is significant in processing strategie.
(4) method of the invention is applicable not only to new nuclear power factory, moreover it is possible to directly apply to in-service nuclear power plant's malfunction protocol Definite value analysis on Uncertainty design in improvement and design.
Detailed description of the invention
Fig. 1 is the process of the illustrative method of the invention that nuclear power plant's accident strategy definite value is determined based on containment operating condition Figure.
Specific embodiment
A specific embodiment of the invention is further illustrated below in conjunction with attached drawing.
Process such as Fig. 1 of the illustrative method of the invention that nuclear power plant's accident strategy definite value is determined based on containment operating condition It is shown, include the following steps.
(1) the parameter definite value nominal value in accident treatment strategy is determined
It is corresponding to the setting of the task or function to be completed in its step fixed based on the analysis to accident treatment strategy Value, and efficiency analysis is carried out by definite value of the accordance analytical calculation to setting, ultimately form the accident treatment of complete set Strategy, and confirm definite value nominal value numerical value therein.
(2) the crucial definite value of accident treatment strategy is screened
Crucial definite value in accident treatment strategy refers to that the execution to accident strategy has decisive meaning, influences whether plan The slightly definite value of implementation effect.Therefore it should judge and filter out the crucial definite value for needing to consider instrument error in accident treatment strategy, And the influence that instrument error generates under containment nominal situation and unfavorable operating condition is analyzed to such definite value.Screening technique includes:
1) it is used for accident diagnosis, determines the trend of accident treatment strategy;
2) judged by definite value, need to execute security function by manual measure to slow down damage sequence;
3) for judging the effect of accident mitigation.
(3) containment nominal situation and unfavorable operating condition circle are determined based on unit design feature and crash analysis conclusion The instrument overall error of crucial definite value in accident treatment strategy is calculated and determined under nominal situation and unfavorable operating condition in limit.Instrument is always missed Difference should count instrument and the trueness error of channel all components, including instrument measurement directional error, isolation module Error, I/O fastener module error and display instrument error.
(4) strategy or definite value are modified in influence of the analysis meter error to accident treatment directive/guide as needed.On the one hand, The influence by the unfavorable operating condition of containment to crucial definite value is needed to take into account.If considering definite value the instrument under nominal situation always Error, it will cause measurement result inaccurate, be unable to envelope and live under the unfavorable operating condition of containment the case where big error occur;Another party Face, it is also necessary to avoid the influence that instrument error under unfavorable operating condition is excessively considered in design process.Method of the invention is for safety Shell nominal situation and the unfavorable operating condition of containment consider correlate meter uncertainty respectively.
(5) definite value accordance analytical calculation is verified
After calculating instrument error, need to confirm by accordance analytical calculation definite value in accident treatment strategy and The acceptable degree of instrument error.If cannot meet the requirements after verifying, the error of instrument has influenced accident treatment strategy It executes, then needs to reselect instrument and analyzed and verified again.
(6) it verifies and confirms
Comprehensive policy validation is carried out finally by the verifying and confirmation of accident treatment strategy, confirmation considers containment operating condition Whether the reasonability of uncertainty definite value, including personnel's intervention time are abundant etc..If cannot be met the requirements after verifying, equally It needs to re-start instrumental analysis and verifying.
The application of the method for the invention that nuclear power plant's accident strategy definite value is determined based on containment operating condition of above-mentioned example It is exemplified below (by taking the narrow range Liquid level of steam generator requires in power generation of fissioning/ATWS response directive/guide as an example).
(1) the parameter definite value nominal value in accident treatment strategy is determined
The range ability of the narrow range liquid level of steam generator is L1~L2(m).Steam generation is required in the accident treatment directive/guide The narrow range water level of device should not have the height of U-tube, that is, be greater than 0% range liquid level.Therefore the parameter in directive/guide is primarily determined Definite value nominal value is L1(m)。
(2) judge and filter out the crucial definite value of accident treatment strategy
Crucial definite value in strategy can generate decisive meaning to the execution of accident strategy, influence whether strategy execution Effect.Range liquid level narrow for steam generator, it is desirable that must not have U-tube, liquid level is in L1(m), which will affect steam The availability of generator, therefore be the key that directive/guide definite value.
(3) instrument error of crucial definite value under containment nominal situation and unfavorable operating condition is determined
Containment operating condition boundary is determined according to unit design feature and to crash analysis conclusion, is calculated and determined normal Under operating condition and unfavorable operating condition in accident treatment strategy crucial definite value instrument overall error.Instrument overall error should be by instrument and channel The trueness error of all components counts, including instrument measurement directional error, isolation module error, I/O fastener module are missed Difference and display instrument error etc..
The narrow range liquid level of steam generator requires not cross U-tube, is greater than L1(m).By calculating, in containment nominal situation Under the conditions of, consider the influence of instrument error, L1(m) δ should be taken when measuring at liquid levelnError;And in the unfavorable working condition of containment Under, instrument is in L1(m) error when measuring at position is δabn
(4) influence of the comprehensive analysis instrument error for accident treatment directive/guide
Step (3) considers error of the instrument under different containment operating conditions respectively, uses nominal situation under nominal situation Instrument error uses the instrument error of unfavorable operating condition under unfavorable working condition, avoids the increase of instrument uncertainty, improve The validity and accuracy of instrument measurement.
The narrow range water level L of steam generator in directive/guide1(m) it is examined respectively under containment nominal situation and unfavorable operating condition Consider, calculates two sets of definite value L1nAnd L1abn.Wherein, L1n=L1n(m), L1abn=L1abn(m).When the reality of steam generator When liquid level is more than the setting valve under corresponding operating condition, secondary side hot trap is restored, and operator can be maintained by control feedwater flow Steam generator water level is stablized.
(5) definite value is verified
The verifying carried out to definite value includes two parts: the verifying of accordance analytical calculation and verification platform verifying.
1) accordance analytical calculation: obtaining under containment is normal and unfavorable operating condition after corresponding instrument error, need through The definite value of the narrow range water level of the evaporator for crossing accordance analytical calculation to confirm above-mentioned analysis and the acceptable journey of instrument error Degree.If that cannot meet the requirements, need to reselect instrument, return step (3) continues to calculate analysis and verifying.
2) verification platform is verified: carrying out comprehensive policy validation finally by the verifying and confirmation of accident treatment strategy, really Recognize the validity of strategy.As that cannot meet the requirements, same return step (3) continues to calculate analysis and verifying, until most Meet verifying eventually to require.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art Mind and range.If in this way, belonging to the model of the claims in the present invention and its equivalent technology to these modifications and changes of the present invention Within enclosing, then the present invention is also intended to include these modifications and variations.Above embodiment only illustrates to of the invention Bright, the present invention can also be implemented with other ad hoc fashions or other particular forms, without departing from the gist of the invention or originally Matter feature.Therefore, the embodiment of description is regarded as illustrative and non-limiting in any way.Model of the invention Enclosing should be illustrated by appended claims, and any variation equivalent with the intention and range of claim should also be included in the present invention In the range of.

Claims (10)

1. a kind of method for determining nuclear power plant's accident strategy definite value based on containment operating condition, which is characterized in that the method packet Include following steps:
(1) the parameter definite value nominal value in accident treatment strategy is determined;
(2) judge and filter out the crucial definite value of accident treatment strategy;
(3) instrument error of crucial definite value under containment nominal situation and unfavorable operating condition is determined;
(4) influence of the instrument error to accident treatment directive/guide under containment nominal situation and unfavorable operating condition is analyzed, as needed Modify tactful definite value;
(5) verifying of definite value accordance analytical calculation is carried out;
(6) it is verified and is confirmed by design verification platform.
2. according to the method described in claim 1, it is characterized by: in step (1), based on the analysis to accident treatment strategy, Corresponding definite value is arranged to the task or function to be completed in its step, and is calculated by accordance and the definite value of setting is carried out Efficiency analysis, ultimately forms the accident treatment strategy of complete set, and confirms definite value nominal value therein.
3. according to the method described in claim 1, it is characterized by: judging and filtering out in accident treatment strategy in step (2) It needs to consider the crucial definite value of instrument error, and instrument under containment nominal situation and unfavorable operating condition is analyzed to such definite value and is missed The influence that difference generates.
4. the method according to claim 1, wherein the screening technique of step (2) includes:
1) it is used for accident diagnosis, determines the trend of accident treatment strategy;
2) judged by definite value, need to execute security function by manual measure to slow down damage sequence;
3) for judging the effect of accident mitigation.
5. according to the method described in claim 1, it is characterized by: being divided in step (3) based on unit design feature and accident Analysis conclusion determines containment nominal situation and unfavorable operating condition boundary, is calculated and determined under nominal situation and unfavorable operating condition at accident The instrument overall error of crucial definite value in reason strategy.
6. according to the method described in claim 5, it is characterized by: in step (3), the instrument overall error should by instrument with And the trueness error of channel all components counts, including instrument measurement directional error, isolation module error, I/O fastener Module error and display instrument error.
7. the method according to claim 1, wherein in step (4):
On the one hand, the influence by the unfavorable operating condition of containment to crucial definite value is needed to take into account, if being considered always definite value normal Instrument error under operating condition, it will cause measurement result inaccurate, be unable to envelope and live under the unfavorable operating condition of containment big error occur The case where;
On the other hand, it is also necessary to avoid the influence that instrument error under unfavorable operating condition is excessively considered in design process.
8. according to the method described in claim 1, it is characterized by: in step (5), for modified definite value in step (4), Firstly, carrying out accordance analytical calculation by calculation procedure to verify crucial definite value and the instrument error in accident treatment strategy Acceptable degree, if verifying after calculated result cannot meet the requirements, at this moment the error of instrument has influenced accident treatment plan Execution slightly, then need to reselect instrument and analyzed and calculated again.
9. according to the method described in claim 1, it is characterized by: finally by design verification platform, being carried out in step (6) The comprehensive dynamic authentication of accident treatment strategy and confirmation confirm the reasonability of directive/guide strategy and definite value, if cannot after verifying It meets the requirements, then needs to re-start instrumental analysis and verifying.
10. according to the method described in claim 9, it is characterized by: in step (6), the uncertainty definite value it is reasonable Property includes whether personnel's intervention time is abundant.
CN201811196532.1A 2018-10-15 2018-10-15 Method for determining accident strategy fixed value of nuclear power plant based on containment working condition Active CN109543941B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201811196532.1A CN109543941B (en) 2018-10-15 2018-10-15 Method for determining accident strategy fixed value of nuclear power plant based on containment working condition

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201811196532.1A CN109543941B (en) 2018-10-15 2018-10-15 Method for determining accident strategy fixed value of nuclear power plant based on containment working condition

Publications (2)

Publication Number Publication Date
CN109543941A true CN109543941A (en) 2019-03-29
CN109543941B CN109543941B (en) 2022-04-19

Family

ID=65844083

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201811196532.1A Active CN109543941B (en) 2018-10-15 2018-10-15 Method for determining accident strategy fixed value of nuclear power plant based on containment working condition

Country Status (1)

Country Link
CN (1) CN109543941B (en)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110993135A (en) * 2019-10-09 2020-04-10 中国核电工程有限公司 Sign-based design method for secondary side heat trap control strategy of pressurized water reactor nuclear power plant
CN111612218A (en) * 2020-04-24 2020-09-01 中国核电工程有限公司 Symptom guide accident guide rule operation strategy optimization method
CN111639831A (en) * 2020-04-20 2020-09-08 中国核电工程有限公司 System expansion application method for containment accident condition treatment
CN111834025A (en) * 2020-07-07 2020-10-27 广东核电合营有限公司 Evaluation method for prolonging cycle of check type supervision project of safety related instrument of nuclear power plant
CN111967711A (en) * 2020-07-07 2020-11-20 中国核电工程有限公司 Method for determining unfavorable working conditions in containment related to accident strategy of pressurized water reactor nuclear power plant
CN112330124A (en) * 2020-10-28 2021-02-05 广东核电合营有限公司 Method and system for evaluating influence of accident environment on uncertainty of instrument channel
CN112598223A (en) * 2020-12-03 2021-04-02 中广核工程有限公司 Nuclear power state oriented law accident rule completeness inspection method and system, electronic equipment and storage medium
CN113421676A (en) * 2021-06-18 2021-09-21 中国核动力研究设计院 Method and device for determining accident procedure setting value of nuclear power plant

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN101217064A (en) * 2007-12-27 2008-07-09 大亚湾核电运营管理有限责任公司 A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant
US20100226468A1 (en) * 2007-06-08 2010-09-09 Rio Gerard Method for determining an uncertainty component relating to power distribution in a nuclear reactor core
US20120109618A1 (en) * 2010-11-02 2012-05-03 Institute Of Nuclear Energy Research, Atomic Energy Council, Executive Yuan Accident parameter identification method for severe accidents
CN104504259A (en) * 2014-12-15 2015-04-08 中国核动力研究设计院 Evaluation method for initiative emission decision of containment vessel in nuclear power plant
CN107103404A (en) * 2017-03-16 2017-08-29 中国核电工程有限公司 A kind of nuclear power plant's accident treatment strategy airworthiness compliance method

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20100226468A1 (en) * 2007-06-08 2010-09-09 Rio Gerard Method for determining an uncertainty component relating to power distribution in a nuclear reactor core
CN101217064A (en) * 2007-12-27 2008-07-09 大亚湾核电运营管理有限责任公司 A fatal accident disposal for improved type gigawatt-level PWR nuclear power plant
US20120109618A1 (en) * 2010-11-02 2012-05-03 Institute Of Nuclear Energy Research, Atomic Energy Council, Executive Yuan Accident parameter identification method for severe accidents
CN104504259A (en) * 2014-12-15 2015-04-08 中国核动力研究设计院 Evaluation method for initiative emission decision of containment vessel in nuclear power plant
CN107103404A (en) * 2017-03-16 2017-08-29 中国核电工程有限公司 A kind of nuclear power plant's accident treatment strategy airworthiness compliance method

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
VINAY KUMAR等: "Parameter Estimation for Quantitative Dependability Analysis of Safety-Critical and Control Systems of NP", 《IEEE TRANSACTIONS ON NUCLEAR SCIENCE》 *
杨萍 等: "秦山核电厂应急操作规程的分析验证和优化建议", 《核技术》 *

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110993135A (en) * 2019-10-09 2020-04-10 中国核电工程有限公司 Sign-based design method for secondary side heat trap control strategy of pressurized water reactor nuclear power plant
CN111639831A (en) * 2020-04-20 2020-09-08 中国核电工程有限公司 System expansion application method for containment accident condition treatment
CN111639831B (en) * 2020-04-20 2024-04-12 中国核电工程有限公司 System expansion application method for handling safety shell accident condition
CN111612218A (en) * 2020-04-24 2020-09-01 中国核电工程有限公司 Symptom guide accident guide rule operation strategy optimization method
CN111612218B (en) * 2020-04-24 2024-05-21 中国核电工程有限公司 Method for optimizing symptom-oriented accident guidance operation strategy
CN111834025B (en) * 2020-07-07 2022-08-23 广东核电合营有限公司 Evaluation method for prolonging cycle of check type supervision project of safety related instrument of nuclear power plant
CN111967711A (en) * 2020-07-07 2020-11-20 中国核电工程有限公司 Method for determining unfavorable working conditions in containment related to accident strategy of pressurized water reactor nuclear power plant
CN111834025A (en) * 2020-07-07 2020-10-27 广东核电合营有限公司 Evaluation method for prolonging cycle of check type supervision project of safety related instrument of nuclear power plant
CN112330124A (en) * 2020-10-28 2021-02-05 广东核电合营有限公司 Method and system for evaluating influence of accident environment on uncertainty of instrument channel
CN112330124B (en) * 2020-10-28 2024-03-12 广东核电合营有限公司 Method and system for evaluating influence of accident environment on uncertainty of instrument channel
CN112598223A (en) * 2020-12-03 2021-04-02 中广核工程有限公司 Nuclear power state oriented law accident rule completeness inspection method and system, electronic equipment and storage medium
CN112598223B (en) * 2020-12-03 2023-08-01 中广核工程有限公司 Nuclear power state guiding method accident regulation completeness checking method, system, electronic equipment and storage medium
CN113421676A (en) * 2021-06-18 2021-09-21 中国核动力研究设计院 Method and device for determining accident procedure setting value of nuclear power plant
CN113421676B (en) * 2021-06-18 2022-05-10 中国核动力研究设计院 Method and device for determining accident procedure setting value of nuclear power plant

Also Published As

Publication number Publication date
CN109543941B (en) 2022-04-19

Similar Documents

Publication Publication Date Title
CN109543941A (en) A method of nuclear power plant's accident strategy definite value is determined based on containment operating condition
CN110163766B (en) Design method of nuclear power plant exception handling strategy
CN110428919A (en) The design method of PWR nuclear power plant reactivity control strategy based on sign
CN110070269B (en) Management optimization method for equipment in post-processing facility based on risk guidance
Montero-Mayorga et al. Effects of RCP trip when recovering HPSI during LOCA in a Westinghouse PWR
EP2643781B1 (en) Full spectrum loca evaluation model and analysis methodology
Fernández-Cosials et al. Time assessment of instrumentation survivability and severe accident guidelines application
Jang et al. An empirical study on the relationships between functional performance measure and task performance measure in NPP MCR
CN107992451B (en) Method for calculating refusing probability of reactor protection system
CN104966158A (en) Screening method for influencing operator nonintervention time sensitive accident
Authén et al. Modelling of DIgital I&C, MODIG—interim report 2015
Dawson Advanced thermal hydraulic simulations for human reliability assessment of nuclear power plants
Tyrväinen et al. Prolonged available time and safe states-State of the art review
Laumann et al. A study on how time pressure and information load affects operators performance in accident scenarios
Lyons et al. Seismic probabilistic risk assessment of nuclear power plants: 10 CFR 50.69 assumptions and sources of uncertainty
Muhlheim et al. Technical Specification Surveillance Interval Extension Using Self-Diagnostics
Agarwal et al. Technical Specification Surveillance Interval Extension of Digital Equipment in Nuclear Power Plants: Review and Research. Light Water Reactor Sustainability Program report
Grelle et al. Development and Testing of Fault-Diagnosis Algorithms for Reactor Plant Systems
Davis et al. ON-Line Monitoring of Instrument Channel Performance: Volume 3: Applications to Nuclear Power Plant Technical Specification Instrumentation
Alrammah The application of probabilistic safety assessment in the preliminary reactor design stage: challenges and insights
Christoph et al. Quality Management, Verification, And Validation Of Structure Mechanical Computer Codes At GRS
Jung et al. A time-reliability correlation for estimating the diagnosis error probability of a nuclear power plant with up-to-date Human–Machine interfaces
Garud State of the Art in CUF-Based Fatigue Assessment & Related Issues From Regulatory and Code Perspectives for Long-Term Operation
Son et al. Application Methods for added Requirement in ASME/ANS RA-Sb-2013 to Internal Flooding PRA
Yuxin et al. Sensitivity Analysis for Human Errors of a Chemical and Volume Control System at Nuclear Power Plant by Soft Control

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant