(INDIAN PRESSURISED WATER REACTOR) Distinguished Scientist & RRF

Slides:



Advertisements
Similar presentations
1 Proprietary and Confidential New Jersey Clean Air Council Public Hearing April 1, 2009 Jeff Halfinger Babcock & Wilcox.
Advertisements

Region II WIN Feb © 2011 Babcock & Wilcox Nuclear Energy, Inc. All rights reserved. A practical, scalable, modular ALWR.
Generic Pressurized Water Reactor (PWR): Safety Systems Overview
India’s nuclear technology export future 1 Panel on Emerging Nuclear Powers September Presenter: S L Rao.
The Harnessed Atom Lesson Six Atoms to Electricity.
BARC IAEA Training Course/Workshop on Natural Circulation in Water Cooled Nuclear Power Plants, ICTP, Trieste, June 25-29,2007 Examples of Natural Circulation.
LFR plant assessment against a Fukushima-like scenario Technical Workshop to Review Safety and Design Aspects of European LFR Demonstrator (ALFRED), European.
1 ACPR Advanced, cost competitive, proven technology, and reliable The Third Generation Nuclear Reactor.
1 MARS © MULTIPURPOSE ADVANCED REACTOR INHERENTLY-SAFE Maurizio Cumo, Federico Santi International Energy Workshop 2004 Paris – June 24, 2004 Potential.
Resource and Energy.
Nuclear Plant Systems ACADs (08-006) Covered Keywords
EXPLOITATION OF GAS HYDRATES AS AN ENERGY RESOURCE K. Muralidhar Department of Mechanical Engineering Indian Institute of Technology Kanpur Kanpur
POWER PLANT TECHNOLOGY INTRODUCTION AND OVERVIEW Prof. Anand Bhatt.
MPMP Power Supply 1 Nuclear Power Update for The Society of American Military Engineers September 15, 2010.
Can Egypt share the Construction of Power Reactors as Korea ?
Energy for the Future Belene NPP Design Features May, 2008 Riviera Holiday Club, Varna, Bulgaria Jordan Georgiev BNPP Manager.
Fukushima Incident Preliminary Analysis, Consequences and Safety Status of Indian NPPs Part-1 Dr. S.K.Jain Chairman & Managing Director NPCIL & BHAVINI.
1 OCCUPATIONAL EXPOSURE at JAPANESE NUCLEAR POWER PLANTS in 2005 October 12, 2006 Shigeyuki Wada Safety Information Division Japan Nuclear Energy Safety.
Chapter 4 Nuclear Energy. Objectives Describe how nuclear fuel is produced. List the environmental concerns associated with nuclear power. Analyze the.
Generation Aino Ahonen CABABILITY OF APROS IN THE ANALYSES OF DIESEL LOADING SEQUENCES E. Raiko, H.Kontio, K.Porkholm, presented by A. Ahonen.
Kevin Burgee Janiqua Melton Alexander Basterash
Nuclear Thermal Hydraulic System Experiment
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Carbon Emissions and the Need for Improved Energy Efficiency.
March 11, 2011 to Present. Presentation Overview Reactor Design and FeaturesChronology of EventsCurrent Status of Each ReactorRecovery Actions Kashiwazaki-Kariwa.
DAVID VAN WAGENER NOVEMBER 26, 2008 CHE 384: TECHNOLOGY REPORT Nuclear Power: Advanced Generations and Outlook.
ERMSAR 2012, Cologne March 21 – 23, 2012 ESTIMATION OF THERMAL-HYDRAULIC LOADING FOR VVER-1000 UNDER SEVERE ACCIDENT SCENARIO Barun Chatterjee 1, Deb Mukhopadhyay.
ERMSAR 2012, Cologne March 21 – 23, 2012 MELCOR Severe Accident Simulation for a “CAREM-like” Integral Reactor M. Caputo, J. M. García, M. Giménez, S.
ERMSAR 2012, Cologne March 21 – 23, 2012 In-vessel retention as retrofitting measure for existing nuclear power plants M. Bauer, Westinghouse Electric.
Reactor pressure vessels of WWER (materials and technology) Janovec, J
Nuclear Battery Battery.  Reactor –Core Metallic fuel core (U-10%Zr) –Reactivity control Movable reflectors –Shutdown system Shutdown rod and reflectors.
NUCLEAR REACTORS G. HETSRONI Emeritus Danciger Professor of Engineering Technion – Haifa – Israel.
ISOE Asian Technical Center 2005ALARA Mini-Workshop Fugen Nuclear Power Station, JAEA- 1 Demonstration of Zinc Injection Technique in Fugen Nuclear Power.
Introduction to Nuclear Energy Candace Davison Senior Reactor Operator Penn State University.
COLLEGE OF ENGINEERING DEPARTMENT OF MECHANICAL ENGINEERING MENB INTRODUCTION TO NUCLEAR ENGINEERING GROUP ASSIGNMENT GROUP MEMBERS: MOHD DZAFIR.
04/16/ Planning New Generation APPA Operations & Engineering Conference April 10, 2006 Jay Hudson, PE Manager, Environmental Management.
Generator Operation. Video of Generator synchronizing.
Advanced Technologies for safer and cleaner Nuclear Energy
REACTOR PRESSURE VESSEL
Prospect of Nuclear Energy in India
Nuclear Power Station A generating station in which nuclear energy is converted into electrical energy. Nuclear reactors, which produce heat by splitting.
REACTOR OPERATIONS LAYOUT OF A REACTOR PLAN
NuScale Generator A Practical Energy Alternative for the Future
1039 GW Power Plant Equivalent
FERROUS AND NON FERROUS ALLOYS
Summary of Int’l ITL Program (1)
AN INTEGRAL PWR, “CAREM”, IS BEING DEVELOPED BY CNEA, ARGENTINA
IAEA International Conference on Fifty Years of Nuclear Power – The next Fifty Years Moscow - Obninsk, Russian Federation - June 28, 2004 Nuclear.
NUCLEAR POWER PLANT SUBMITED BY…. ANJALI PRAKASH EN 3rd YEAR
Date of download: 11/7/2017 Copyright © ASME. All rights reserved.
FERROUS AND NON FERROUS ALLOYS
Collaborative Research in
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
Solutions for Nuclear Power Industry
Nuclear Power - a reliable partner
Thomas MAZOUR IAEA, Div of Nuclear Power/NPES
Nuclear Power Update for The Society of American Military Engineers
IVR Design and Safety Demonstration of Advanced NPPs in China
Circular Economy Development in China
Dan Keuter Vice-President, Planning & Innovation Entergy Nuclear
Reactor Experiments Instructor: Prof. Kune Y. Suh T/A : Sang Hyuk Yoon
BASIC PROFESSIONAL TRAINING COURSE Module III Basic principles of nuclear safety Case Studies Version 1.0, May 2015 This material was prepared.
LOW-POWER RESEARCH REACTOR FOR EDUCATION AND TRAINING
Session Name: Lessons Learned from Mega Projects
VICTOR HUGO SANCHEZ ESPINOZA and I. GÓMEZ-GARCÍA-TORAÑO
NUMERICAL STUDY OF IN-VESSEL CORIUM RETENTION IN A BWR REACTOR M
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
Generation of Most Eligible Steam for Rankine Cycle
THE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS Moustafa Aziz Nuclear and Radiological Regulatory Authority.
Be Frank on Reconciliation or Breakup ……
Presentation transcript:

(INDIAN PRESSURISED WATER REACTOR) Distinguished Scientist & RRF IPWR (INDIAN PRESSURISED WATER REACTOR) Dr A B Mukherjee Ex-Director, RPG, BARC Distinguished Scientist & RRF

World electricity generation by fuel (International Energy Authority)

Challenges of 21st century Thermal power plant Global Scenario: International policy deliberation is proposing to reduce the level of CO2 emission for power generation to below 50g/kWh by 2050. Currently the global average rate of CO2 emission by thermal power plant is 500g/kWh. About 66 % of electricity is produced by thermal power plants.

Challenges of 21st century Thermal power plant Indian Scenario: CO2 emission by thermal power plant : 1000g/kwh. Value may jump 20-30% high at user end. Currently about 65 % of electricity is produced by thermal power plants. Mix mode using Nuclear, renewable, hydro and “Carbon Based” is the only option to meet the level of 50g/kWh by 2050. Nuclear power needs to play a major role like base load plant.

Indian PHWR

INDIAN PRESSURIZED WATER REACTOR (IPWR) Our Strength :- Expertise available for design, construction and operation of PHWRs. Experience gained in commissioning, operating and maintenance of LWRs. Expertise available for development/ making critical equipment indigenously. Fuel fabrication technology is well established. 6

Pressurised Water Reactor Schematic View of PWR

Pressurised Water Reactor Only nuclear island is different involving RPV, CRDM, fuel etc. The design of SG and beyond will remain same and can be adopted from the PHWR technology. . Schematic View of PWR

Primary Coolant Circulating Loop of IPWR RPV : Reactor Pressure Vessel ECCS : Emergency Core Cooling System RCP : Re-circulating Coolant Pump CVCS : Chemical and Volume Control System SG : Steam Generator RHRS : Residual Heat Removal System HPIS : High Pressure Injection System

Conceptual Design of Reactor & Primary systems ( Nuclear island) Completion of preliminary safety analysis and approval by Regulator Review and resolution of interfaces Detail design& development of Systems and components Development of long lead items like RPV. Approach for IPWR

IPWR - Salient safety Features Passive heat removal under prolonged Station Black Out - Plant Autonomy for 7 days Air cooled elevated DG set 4 independent trains of Engineered Safety System (like ECCS) with independent power source Philosophy for Severe Management Accident Hydrogen mitigation Containment pressure management (Filtered Hard Vent) Core catcher

MAJOR DEVELOPMENTS IDENTIFIED RPV Forging development RPV Fabrication Technology development Structural and Thermal Hydraulic Analyses Core & Fuel Assembly development Control & shut-off Rods & Drive development Passive Safety systems development

Development of Low Alloy Steel Forgings for RPV of Indian PWR (IPWR) Aim is to : Establish process plans for Melting, Forging, HT & Quality Control Make prototype scale Forgings Optimize process plans Qualify material & technology by comprehensive testing.

Development of thick low alloy steel forgings for IPWR pressure vessel Stages Two forgings to be developed 340 mm thick – represents nozzle portion 750 mm thick – represents flange 750 4500 340 Low alloy steel Grade – 20MnMoNi55 – equivalent to SA508 Grade 3 Class 1 Quenched and tempered steel (Bainitic steel) C Mn Si P S Cr Mo Ni V Al 0.15- 0.25 1.15- 1.55 0.10- 0.35 0.008 max 0.20 max 0.40- 0.55 0.45- 0.85 0.02 max 0.01- 0.04

Forging Forging sequence Cast Ingot Ring rolling over mandrel Final Shell after forging process

Through thickness tensile test Location : Through thickness, 0T/2, T/4, T/2, 3T/4 and 4T/4 Direction : Axial QT PWHT YS UTS RT 350 All through thickness tensile tests results meet the requirements

Through thickness charpy “V” notch impact test Through thickness impact test Direction – Axial Temperature- -12oC PWHT max condition All through thickness impact test results meet the requirements

Challenges of IPWR Cost reduction completing greater portions of the detailed design prior to construction involving manufacturers. using a proven supply chain from PHWR series Compensation for low Carbon attributes.

CONCLUSIONS Indian PHWR program has demonstrated the maturity achieved in the research, design, development and successful commercial deployment of nuclear technology in the country. Along with imported Light Water Reactors (LWRs) , India has also initiated activities related to development of indigenously designed PWRs to meet the country’s immediate energy demand. India’s Nuclear Power Program needs to play important role to achieve CO2 limit of 50g/kwh.

THANK YOU

RPV FORGING DEVELOPED BY RPG/BARC LAS forgings (Cr-Mo-V Class) Developed indigenously at HEC, Ranchi Largest size developed first time within the country – 120 T ingot Fabrication Technology for vessel developed & deployed on the project Shell Forging Bottom Dished Head

PWR Programme in India Operating LWRs based on foreign technical cooperation GE- BWR (TAPS-1&2) VVER (KK-1 )-PWR Planned PWRs based on foreign technical cooperation VVER AP1000 EPR Indigenous design and development of PWR Indian PWR (IPWR), a joint project of BARC & NPCIL

IPWR : Plant Specification General plant data Reactor thermal output : 2700 MWth Design pressure :17.7 MPa Design temperature : 350 °C Service life : 60 calender years Primary heat transport system data Primary coolant flow rate : 76,700 m3/h Reactor operating pressure : 15.7 MPa Average temperature of Coolant : 308 °C No. of loops : 4 (one vertical SG and one PCP in each loop)

Accident Scenarios Considered SBO-after Safe Shut Down Passive Decay Heat Removal System (PDHRS) LOCA- after Safe Shut Down Emergency Core Cooling System (ECCS) BDBA Corium Retention and Core Catcher System

International Energy Authority-15

Electrical power as on March-2018 ( Report CEA-18) Energy Source MW % of total Coal 222907 64.8 nuclear 6780 1.97 hydro 45293 13.17 Renewable ( Wind, small hydro, solar etc) 69022 20 Total 344002