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REACTOR PRESSURE VESSEL

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Presentation on theme: "REACTOR PRESSURE VESSEL"— Presentation transcript:

1 REACTOR PRESSURE VESSEL

2 REACTOR PRESSURE VESSEL
RPV IS A UNIQUE COMPONENT, AS : NUCLEAR REACTION IS REALIZED INSIDE RPV RPV CONTAINS WHOLE NUCLEAR FISSION MATERIALS RPV CONTAINS PRACTICALLY ALL RADIOACTIVELY INDUCED MATERIALS RPV CANNOT BE PRACTICALLY COOLED DOWN IF IT RUPTURED, THEN NON-CONTROLLED CORE MELTING TAKES PLACE

3 REACTOR PRESSURE VESSEL
DUE TO A LARGE VOLUME OF REACTOR ACTIVE CORE TO PRODUCE REQUIRED HEAT OUTPUT, AND DUE TO HIGH OPERATION CONDITIONS: RPV IS A LARGE AND HEAVY COMPONENT RPV IS PRACTICALLY NON-REPLACEABLE MUST BE SAFE DURING WHOLE LIFETIME RPV MUST FULFIL THE MOST SEVERE REQUIREMENTS TO MATERIAL QUALITY

4 RPV PARAMETERS

5 RPV CODES ASME Boiling and Pressure Vessel, Section III – Nuclear Power Plant Components KTA – Safety Standards for Components of the Reactor Coolant Pressure Boundary of Light Water Reactors Japanese Society of Mechanical Engineers, JSME Codes for Nuclear Power Generation Facilities, Rules on Design and Construction for Nuclear Power Plant

6 ISI CODES ASME Section XI - "Rules for In-service Inspection of Nuclear Power Plant Components” RSE-M - “Rules for In-Service Inspection for Mechanical Components of PWR Nuclear Island”

7 WWER RPV CODES Rules for Design and Safe Operation of Components of NPPs, Test and Research Reactors and Stations, 1973, 1989, 2000 Code for Strength Calculations of Components of Reactors, Steam-Generators and Pipings of NPPs, Test and Research Reactors and Stations, 1973, 1989 VERLIFE – Unified Procedure for Lifetime Assessment of Components and Piping in WWER type NPPs during Operation, 2003, 2008, IAEA-NULIFE-VERLIFE

8 DIFFERENCE BETWEEN PWR AND WWER RPV
KWU

9 OUTLET NOZZLES INLET NOZZLES

10 DIVIDING RING

11 TYPICAL TECHNOLOGY PROCESS FOR WWER-1000 RPV
Upper part of RPV welding of circumferential welds anticorrosive cladding mechanical and heat treatment quality inspection Lower part of RPV RPV assembly 1. welding of circumferential weld no.4 anticorrosive cladding of a zone under weld no.4 TYPICAL TECHNOLOGY PROCESS FOR WWER-1000 RPV BottomДнище Lower core shell Upper core shell Support shell Lower nozzle shell Upper nozzle shell Flange shell

12 PWR weld weld NOZZLE FORGING WWER-1000 WWER-440

13 RPV STRESSORS

14 CREEP & RELAXATION

15 FATIGUE

16 THERMAL AGEING

17 IRRADIATION DAMAGE

18 CORROSION

19 WEAR & EROSION

20 STRESS CORROSION CRACKING

21 WWER PWR

22 TYPICAL CIRCUMFERENTIAL FLUX DISTRIBUTION IN PWR

23 WWER FLUX DISTRIBUTION IN LOW-LEAKAGE CORES
23

24 NEUTRON FLUENCES

25 TYPICAL AXIAL FLUX DISTRIBUTION IN WWER

26 TRANSITION TEMPERATURES
PWR: NIL DUCTILITY TEMPERATURE RTNDT WWER: CRITICAL TEMPERATURE OF BRITTLENESS Tk

27 RPV MATERIALS PWR: ASME: KTA: RCC-M: (ASME) SA 302 Grade B
ASME SA 533 Grade B Class 1 ASME SA 508 Class 2 KTA: 22NiMoCr37, 20MnMoNi55 RCC-M: 16MnD5

28 RPV MATERIALS WWER: WWER-440 15Kh2MFA(A) , 18Kh2MFA – Cr-Mo-V type
15Kh2NMFA(A) – Ni-Cr-Mo-V type

29 RPV MATERIALS

30 RPV MATERIALS trend in decrease of Cu+P contents

31 QUALIFICATION TEST PROGRAMME
TENSILE TESTS NOTCH IMPACT TESTS FRACTURE TOUGHNESS TESTS FATIGUE TESTS CORROSION TESTS IRRADIATION DAMAGE STUDY THERMAL AGEING STUDY

32 ACCEPTANCE TEST PROGRAMME
TENSILE TEST ROOM & DESIGN TEMPERATURE NOTCH IMPACT TESTS ROOM TEMPERATURE DETERMINATION OF Tk OR CONFIRMATION OF Tk DROP WEIGHT TESTS RESISTANCE TO INTERCRYSTALLINE CORROSION

33 MONITORING DAMAGE IN RPV
PRESSURE AND TEMPERATURE RECORDING SURVEILLANCE SPECIMEN PROGRAMME NEUTRON DOSIMETRY IN OUTER WALL IN-SERVICE INSPECTION VIBRATION MONITORING


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