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Module001-BWR01-K0002

Boiling Water Reactor (systems) BWR

Werkvorm Doelgroep Tijdsduur

:Z/S/K : :

versie 1.0 27 Januari 2007 Paul van der Kraan

Staat van wijzigingenVersienummer 0.0 1.0 Datum 06 April 2005 27 januari 2007 Wijzigingen concept conversie FM Auteur P. van der Kraan P. van der Kraan

Deze publicatie is eigendom van: Paul van der Kraan Valge 46 9965 PG Leens telefoon: +31(0)595 571 117 Paul van der Kraan 2006

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Module - Boiling Water Reactor (systems)

IntroductionThis syllabus is aimed at the group students following a course to obtain a degree as a bachelor of engineering. The realization of this document is triggered by the Hanze University. They asked me to prepare some classes for the International Power Generation Development Group (IPGD) in the city of Groningen. I have been working in the Dodewaard Nuclear Power Plant for over 10 years, in the operational management and also at the training department. Due to the question from the Hanze University I got aware of the fact that the knowledge of the nuclear technology in Holland is very poor. I hope that as a result of this syllabus some of the students get interested in the nuclear technology to regain a level of knowledge what gives a positive contribution to the development of new power plants around the world and specially a new nuclear power plant in the Netherlands on short terms.

Paul van der Kraan

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Module - Boiling Water Reactor (systems)

ContentsIntroduction . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . Abbreviations . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 Boiling water reactor systems . . . . . . . . . . . . . . . . . . . . . . . . .1.1 1.2 1.3 1.4 1.5 1.6 1.7 1.8 1.9 Boiling water reactor plant . . . . . . . . . . . . . . . . 1.1.1 BWR Reactor Vessel Assembly . . . . . . . . Reactor Water Cleanup System . . . . . . . . . . . . . Decay Heat Removal . . . . . . . . . . . . . . . . . . . . Reactor Core Isolation Cooling . . . . . . . . . . . . . Standby Liquid Control System . . . . . . . . . . . . . Emergency Core Cooling Systems . . . . . . . . . . . High Pressure Emergency Core Cooling Systems . Low Pressure Emergency Core Cooling Systems . Boiling Water Reactor Containments . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3 7 1313 13 17 18 19 20 20 23 23 24

Module - Boiling Water Reactor (systems)

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Module - Boiling Water Reactor (systems)

AbbreviationsABWR ACS ADS AIWA ALARA APR APRM ARD ARM ASD ASME ATIP ATLM ATP ATWS B&V BOP BWR CAM CCC CDF CFS C&I CO COE COPS CP CPR CRD CRDHS CRT CSP CST CTG CWS DAT DBA DCPS DCV DG DMC DRM DW DWC - Advanced Boiling Water Reactor - Atmospheric Control System - Automatic Depressurization System - AC-Independent Water Addition System - As Low As Reasonably Achievable - Automatic Power Regulator System - Average Power Range Monitor - Anti-Reverse Rotation Device - Area Radiation Monitoring - Adjustable Speed Drive - American Society of Mechanical Engineers - Automatic Traversing In-Core Probe - Automatic Thermal Limit Monitor System - Authorization to Proceed - Anticipated Transients Without Scram - Black and Veatch - Balance-of-Plant - Boiling Water Reactor - Containment Atmospheric Monitoring System - Control Cell Core - Core Damage Frequency - Condensate and Feedwater System - Control and Instrumentation - Commercial Operation - Cost of Electricity - Containment Overpressure Protection System - Construction Permit - Critical Power Ratio - Control Rod Drive - Control Rod Drive Hydraulic System - Cathode Ray Tube - Condensate Storage Pool - Condensate Storage Tank - Combustion Turbine Generator - Circulating Water System - Design Acceptance Test - Design Basis Accident - DC Power Supply - Drywell Connecting Vent - Diesel Generator - Digital Measurement Controller - Solid Radwaste Management - Drywell - Drywell Cooling

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EABWR ECCS ECP ECW EDG EHC EMI EMS EPD EPRI EUR FCS FDA FFTR FIV FLD FMCRD FOAKE FP FPCU FSAR FSC FTDC FW FWP FWC GEIEMS GETAB GNP GPM HCW HIC HCU HPCF HPCP HPCS HPIN HVAC HWC IASCC IGSCC ILRT IMS IRM ISI ITAAC LCW LD

- European Advanced Boiling Water Reactor - Emergency Core Cooling System - Electrochemical Potential - Emergency Chilled Water - Emergency Diesel Generator - Electro-hydraulic Control (Turbine Control System) - Electro-Magnetic Interference - Essential Multiplexing System - Electrical Power Distribution - Electric Power Research Institute - European Utility Requirements - Flammability Control System - Final Design Approval - Final Feedwater Temperature Reduction - Flow-Induced Vibration - Fuel Loading - Fine Motion Control Rod Drive - First-of-a-Kind Engineering - Fire Protection - Fuel Pool Cooling and Cleanup - Final Safety Analysis Report - First Structural Concrete - Fault Tolerant Digital Controller - Feedwater - Feedwater Pump - Feedwater Control System - General Electric Integrated Equipment Monitoring System - General Electric Thermal Analysis Basis - Gross National Product - Gallons per minute - High-Conductivity Waste - High Integrity Container - Hydraulic Control Unit - High Pressure Core Flooder - High Pressure Condensate Pump - High Pressure Core Spray - High Pressure Nitrogen Gas Supply - Heating, Ventilation and Air-Conditioning - Hydrogen Water Chemistry I&C Instrumentation and Control - Irradiation-Assisted Stress Corrosion Cracking - Intergranular Stress Corrosion Cracking - Integrated Leak Rate Test - Information Management System - Intermediate Range Monitor - In-Service Inspection - Inspection, Test, Analysis and Acceptance Criteria - Low-Conductivity Waste - Lower Drywell

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Module - Boiling Water Reactor (systems)

LDI LHGR LLRT LOCA LOPP LOOP LPCI LPCP LPCRD LPFL LPRM LRM MCC MCES MCR MCPR M-G MITI MLHGR MMI MOV MRBM MS MSIV MUW MUX MWB NBS NCW NDT NEMS NMS NRC NRHX NSPS NSS NUMAC NUPEC OG OL O&M OPRM PCI PCS PCT PCV PCV PG

- Leak Detection and Isolation System - Linear Heat Generation Rate - Local Leak Rate Test - Loss-of-Coolant Accident - Loss of Preferred Power - Loss of Offsite Power - Low-Pressure Coolant Injection - Low-Pressure Condensate Pump - Locking Piston Control Rod Drive - Low Pressure Flooder - Local Power Range Monitor - Liquid Radwaste Management System - Main Control Console - Main Condenser Evacuation System - Main Control Room - Minimum Critical Power Ratio - Motor-Generator - Ministry of International Trade and Industry (Japan) - Maximum Linear Heat Generation Rate - Man-Machine Interface - Motor-Operated Valve - Multi-Channel Rod Block Monitoring System - Main Steam System - Main Steam Isolation Valve - Makeup Water System - Multiplexer - Makeup Water Building - Nuclear Boiler System - Normal Chilled Water - Nil Ductility Temperature - Non-Essential Multiplexing System - Neutron Monitoring System - Nuclear Regulatory Commission - Non-Regenerative Heat Exchanger - Nuclear System Protection System - Nuclear Steam Supply - Nuclear Measurement Analysis and Control - Japan Nuclear Power Engineering Test Center - Offgas - Operating License - Operation and Maintenance - Oscillation Power Range Monitor - Pellet Clad Interaction - Plant Computer System - Peak Fuel Clad Temperature - Primary Containment Volume - Primary Containment Vessel - Power Generation (loads)

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PGCS PIP PIP PLR POWRTRAK PSAR PSTF PRA PRM PRNM PWR RAT RBCW RBSW RCIC RCIR RCIS RCCV RCPB RFC RHR RHX RIP RMC RMISS RMP RMU RPS RPV RRCS RSBW RSS RTNDT RWCU RWM S&PC SAR SBO SBPC SCC SCRRI SDV SGTS SHE SJAE SLCS SOE SP

- Power Generation Control System - Plant Investment Protection (loads) - Position Indicator Probe - Part Length Fuel Rod - Electronic Configuration Management - Preliminary Safety Analyses Report - Pressure Suppression Test Facility - Probabilistic Risk Assessment - Process Radiation Monitoring System - Power Range Neutron Monitor System - Pressurized Water Reactor - Reserve Auxiliary Transformer - Reactor Building Cooling Water System - Reactor Building Service Water System - Reactor Core Isolation Cooling System - Reactor Recirculation System - Rod Control and Information System - Reinforced Concrete Containment Vessel - Reactor Coolant Pressure Boundary - Recirculation Flow Control System - Residual Heat Removal System - Regenerative Heat Exchanger - Reactor Internal Pump - Recirculation Motor Cooling - Recirculation Motor Inflatable Shaft Seal - Recirculation Motor Purge - Remote Multiplexer Unit - Reactor Protection System - Reactor Pressure Vessel - Redundant Reactivity Control System - Reactor Building Service Water System - Remote Shutdown System - Reference Nil Ductility Temperature - Reactor Water Cleanup System - Rod Worth Minimizer System - Steam and Power Conversion System - Safety Analysis Report - Station Blackout - Steam Bypass and Pressure Control System - Stress Corrosion Cracking - Select Control Rod Run-in - Scram Discharge Volume - Standby Gas Treatment System - Standard Hydrogen Electrode - Steam Jet Air Ejector - Standby Liquid Control System - Sequence of Events - Suppression Pool

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Module - Boiling Water Reactor (systems)

SPCU SPDS SRM SRNM SRV SRW SSAR SSE SSLC SW TBCW TBS TBSW TEPCO TGSS TIP TIU TOC TPC TSW UAT UD UHS UPS UTP URD VAC VB V&V WDP WRNM WW

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