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GB/T 50663-2011   Technical code for engineering hydrology for nuclear power plant (English Version)
Standard No.: GB/T 50663-2011 Status:valid remind me the status change

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,,2012-3-1,14113818190031C59E5ECBB782EF4
Standard No.: GB/T 50663-2011
English Name: Technical code for engineering hydrology for nuclear power plant
Chinese Name: 核电厂工程水文技术规范
Chinese Classification: P12    Engineering hydrology
Professional Classification: GB    National Standard
Source Content Issued by: MOHURD
Issued on: 2011-02-18
Implemented on: 2012-3-1
Status: valid
Target Language: English
File Format: PDF
Word Count: 20000 words
Translation Price(USD): 370.0
Delivery: via email in 1 business day
1 General Provisions 1.0.1 This code is formulated with a view to implementing the laws, regulations and technical economy policy of the construction of relevant national nuclear power plant, meeting the safety requirements for the design construction and operation of nuclear power plant engineering, unifying the content, method, depth and technology requirements of hydrological survey, analysis and calculation, guaranteeing the design technique level and quality of engineering hydrological survey, and achieving safety and usability, technical advancement and economic rationality. 1.0.2 This code is applicable to the hydrological survey, analysis and calculation work of water supply-source, flood control at plant site, fluvial process and beach stability of fixed commercial land nuclear power plant engineering of various reactor types. 1.0.3 Local measured hydrological information and survey information shall be the main criterion for the hydrological survey, analysis and calculation of nuclear power plant engineering. Measured information of adjacent or similar basin may be selected for referential evidence where measured information has a shortage, but the representativeness of reference station information for engineering point shall be analyzed; observation station shall be established adjacent to engineering point where necessary, and observation items, content, method and cycle shall be carried out according to the characteristics and requirements of hydrological survey of nuclear power plant. 1.0.4 The basic hydrological information, adopted in hydrological survey, analysis and calculation of nuclear power plant engineering shall be analyzed in terms of the reliability, consistency and representativeness. Method selection and parameter calibration in the process of calculation and analysis shall be carried out according to local hydrology and related condition; the safety and rationality of calculation and analysis shall be guaranteed. 1.0.5 During construction and operation phase of nuclear power plant, where historical infrequent hydrological event happens, design organization shall timely survey and collect relevant information to recheck the original calculated result, correct original calculated result where necessary and propose countermeasures jointly with relevant personnel. 1.0.6 Hydrological survey, analysis and calculation of nuclear power plant engineering shall not only comply with this code, but also comply with those specified in the current relevant standards of the state.   2 Terms 2.0.1 Nuclear safety Completing the correct operation condition and accident prevention or relieving the accident consequence so as to protect the site personnel, the public and environment from excessive radiation hazards. 2.0.2 Safety system As an important system for safety, it is used to ensure an safe shutdown of the reactor, to discharge the residual heat from reactor core or to restrict the consequences of anticipated operation event and accident condition. 2.0.3 Design basis Design parameter value determined for reaching the design standard of nuclear safety important items. 2.0.4 Deterministic method It's a method that the majority of parameters and their values may be determined by mathematical method and clarified through physical relationship. 2.0.5 Probabilistic method Probability distribution model is adopted to analyze hydrographical features sequence and calculate design parameter. 2.0.6 Design basis flood The flood selected for determining the design basis of nuclear power plant. 2.0.7 Residual heat The sum of heat generated by fission after radioactive decay and shutdown and that stored in the reactor structural material and heat transfer medium. 2.0.8 Final heat sink The atmosphere or water or the combination of both accepting the residual heat discharged by nuclear power plant. 2.0.9 Hydrological survey On-site information collection, reconnaissance, investigation and measuring etc. conducted to master basic hydrological information.  
Foreword I 1 General Provisions 2 Terms 3 Hydrological Survey 3.1 General Requirement 3.2 Storm Surge, Tsunami and Wave Survey 3.3 Land Flood Survey 3.4 Low-water Survey 3.5 Water Resource Survey 3.6 Beach Change Survey 3.7 Ice Regime Survey 4 Design Basis Flood 4.1 General Requirement 4.2 High Astronomical Tide 4.3 Sea Level Abnormality 4.4 Storm Surge 4.5 Seiche Surge 4.6 Tsunami or Lake Surge 4.7 Run-off Flood 4.8 Dam-break Flood 4.9 Wave Impact 4.10 Flood Caused by Potential Natural Factors 4.11 Impact of Human Activities on Flood 4.12 Storm Flood of Small Basin 4.13 Surface Waterlogging 4.14 Combinatorial Analysis of Flood Event 5 Design Basic Low Water Level 5.1 General Requirement 5.2 Low Astronomical Tide 5.3 Negative of Storm Surge 5.4 Negative of Seiche 5.5 Negative of Tsunami or Lake Surge 5.6 Wave Impact 5.7 River, Reservoir and Lake Low-flow 5.8 Low-flow Caused by Potential Natural Factors 5.9 Impact of Human Activities on Low-flow 5.10 Combinatorial Analysis of Low-flow Event 6 Water Source 6.1 General Requirement 6.2 Natural River 6.3 Upstream of Reservoir or Sluice 6.4 Downstream of Sluice and Dam 6.5 Rivers in River Network Region 6.6 Lake 6.7 Sea 6.8 Impact of Human Activities on Water Source 6.9 Water Temperature, Sediment, Water Quality and Salinity 7 Sediment and Beach Stability 7.1 General requirement 7.2 Characteristics of Water Flow and Sediment 7.3 Simulation of Water Flow Movement 7.4 Riverbed Variation of Shore Segment of Site Design 7.5 Seabed Variation of Shore Segment of Site Design 7.6 Impact of Human Activities on Beach Stability 7.7 Intake and Discharge Condition Analysis 8 Hydrological Observation and Special Station 8.1 General Requirement 8.2 Hydrometry for Coastal and Tidal Estuary 8.3 Hydrometry for River 8.4 Marine Hydrological Station 8.5 Land Hydrological Station 9 Contents and Requirements at Each Stage of Nuclear Power Plant 9.1 General Requirement 9.2 Site Survey Stage 9.3 Preliminary Feasibility Study Stage 9.4 Feasibility Study Stage 9.5 Preliminary Design Stage 9.6 Construction Drawing Design Stage Explanation of Provisions List of Quoted Standards
Referred in GB/T 50663-2011:
* GB/T 12763-
* GB 50660-2011 Code for Designing large and Middle Fossil Fuel Power Plant
Code of China
Standard
GB/T 50663-2011  Technical code for engineering hydrology for nuclear power plant (English Version)
Standard No.GB/T 50663-2011
Statusvalid
LanguageEnglish
File FormatPDF
Word Count20000 words
Price(USD)370.0
Implemented on2012-3-1
Deliveryvia email in 1 business day
Detail of GB/T 50663-2011
Standard No.
GB/T 50663-2011
English Name
Technical code for engineering hydrology for nuclear power plant
Chinese Name
核电厂工程水文技术规范
Chinese Classification
P12
Professional Classification
GB
ICS Classification
Issued by
MOHURD
Issued on
2011-02-18
Implemented on
2012-3-1
Status
valid
Superseded by
Superseded on
Abolished on
Superseding
Language
English
File Format
PDF
Word Count
20000 words
Price(USD)
370.0
Keywords
GB/T 50663-2011, GB 50663-2011, GBT 50663-2011, GB/T50663-2011, GB/T 50663, GB/T50663, GB50663-2011, GB 50663, GB50663, GBT50663-2011, GBT 50663, GBT50663
Introduction of GB/T 50663-2011
1 General Provisions 1.0.1 This code is formulated with a view to implementing the laws, regulations and technical economy policy of the construction of relevant national nuclear power plant, meeting the safety requirements for the design construction and operation of nuclear power plant engineering, unifying the content, method, depth and technology requirements of hydrological survey, analysis and calculation, guaranteeing the design technique level and quality of engineering hydrological survey, and achieving safety and usability, technical advancement and economic rationality. 1.0.2 This code is applicable to the hydrological survey, analysis and calculation work of water supply-source, flood control at plant site, fluvial process and beach stability of fixed commercial land nuclear power plant engineering of various reactor types. 1.0.3 Local measured hydrological information and survey information shall be the main criterion for the hydrological survey, analysis and calculation of nuclear power plant engineering. Measured information of adjacent or similar basin may be selected for referential evidence where measured information has a shortage, but the representativeness of reference station information for engineering point shall be analyzed; observation station shall be established adjacent to engineering point where necessary, and observation items, content, method and cycle shall be carried out according to the characteristics and requirements of hydrological survey of nuclear power plant. 1.0.4 The basic hydrological information, adopted in hydrological survey, analysis and calculation of nuclear power plant engineering shall be analyzed in terms of the reliability, consistency and representativeness. Method selection and parameter calibration in the process of calculation and analysis shall be carried out according to local hydrology and related condition; the safety and rationality of calculation and analysis shall be guaranteed. 1.0.5 During construction and operation phase of nuclear power plant, where historical infrequent hydrological event happens, design organization shall timely survey and collect relevant information to recheck the original calculated result, correct original calculated result where necessary and propose countermeasures jointly with relevant personnel. 1.0.6 Hydrological survey, analysis and calculation of nuclear power plant engineering shall not only comply with this code, but also comply with those specified in the current relevant standards of the state.   2 Terms 2.0.1 Nuclear safety Completing the correct operation condition and accident prevention or relieving the accident consequence so as to protect the site personnel, the public and environment from excessive radiation hazards. 2.0.2 Safety system As an important system for safety, it is used to ensure an safe shutdown of the reactor, to discharge the residual heat from reactor core or to restrict the consequences of anticipated operation event and accident condition. 2.0.3 Design basis Design parameter value determined for reaching the design standard of nuclear safety important items. 2.0.4 Deterministic method It's a method that the majority of parameters and their values may be determined by mathematical method and clarified through physical relationship. 2.0.5 Probabilistic method Probability distribution model is adopted to analyze hydrographical features sequence and calculate design parameter. 2.0.6 Design basis flood The flood selected for determining the design basis of nuclear power plant. 2.0.7 Residual heat The sum of heat generated by fission after radioactive decay and shutdown and that stored in the reactor structural material and heat transfer medium. 2.0.8 Final heat sink The atmosphere or water or the combination of both accepting the residual heat discharged by nuclear power plant. 2.0.9 Hydrological survey On-site information collection, reconnaissance, investigation and measuring etc. conducted to master basic hydrological information.  
Contents of GB/T 50663-2011
Foreword I 1 General Provisions 2 Terms 3 Hydrological Survey 3.1 General Requirement 3.2 Storm Surge, Tsunami and Wave Survey 3.3 Land Flood Survey 3.4 Low-water Survey 3.5 Water Resource Survey 3.6 Beach Change Survey 3.7 Ice Regime Survey 4 Design Basis Flood 4.1 General Requirement 4.2 High Astronomical Tide 4.3 Sea Level Abnormality 4.4 Storm Surge 4.5 Seiche Surge 4.6 Tsunami or Lake Surge 4.7 Run-off Flood 4.8 Dam-break Flood 4.9 Wave Impact 4.10 Flood Caused by Potential Natural Factors 4.11 Impact of Human Activities on Flood 4.12 Storm Flood of Small Basin 4.13 Surface Waterlogging 4.14 Combinatorial Analysis of Flood Event 5 Design Basic Low Water Level 5.1 General Requirement 5.2 Low Astronomical Tide 5.3 Negative of Storm Surge 5.4 Negative of Seiche 5.5 Negative of Tsunami or Lake Surge 5.6 Wave Impact 5.7 River, Reservoir and Lake Low-flow 5.8 Low-flow Caused by Potential Natural Factors 5.9 Impact of Human Activities on Low-flow 5.10 Combinatorial Analysis of Low-flow Event 6 Water Source 6.1 General Requirement 6.2 Natural River 6.3 Upstream of Reservoir or Sluice 6.4 Downstream of Sluice and Dam 6.5 Rivers in River Network Region 6.6 Lake 6.7 Sea 6.8 Impact of Human Activities on Water Source 6.9 Water Temperature, Sediment, Water Quality and Salinity 7 Sediment and Beach Stability 7.1 General requirement 7.2 Characteristics of Water Flow and Sediment 7.3 Simulation of Water Flow Movement 7.4 Riverbed Variation of Shore Segment of Site Design 7.5 Seabed Variation of Shore Segment of Site Design 7.6 Impact of Human Activities on Beach Stability 7.7 Intake and Discharge Condition Analysis 8 Hydrological Observation and Special Station 8.1 General Requirement 8.2 Hydrometry for Coastal and Tidal Estuary 8.3 Hydrometry for River 8.4 Marine Hydrological Station 8.5 Land Hydrological Station 9 Contents and Requirements at Each Stage of Nuclear Power Plant 9.1 General Requirement 9.2 Site Survey Stage 9.3 Preliminary Feasibility Study Stage 9.4 Feasibility Study Stage 9.5 Preliminary Design Stage 9.6 Construction Drawing Design Stage Explanation of Provisions List of Quoted Standards
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