1 BREI Conducted Comprehensive Independent Reviews of Passive Heat Removal Systems with Ejectors-Condensers Euratom DEEPSSI Project for the design and.

Slides:

Advertisements

Similar presentations

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

Advertisements

NuScales Passive Safety Approach Update September 2011 Contact Information: Bruce Landrey Chief Marketing Officer Dr. Jose N.

Generic Pressurized Water Reactor (PWR): Safety Systems Overview

FRENCH PWR’S ULTIMATE HEAT SINKS THREATENED BY THEIR ENVIRONMENT

Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.

ANGRA 1 E 2 ANGRA 3 NOVAS USINAS Session V Overview of Fukushima Response Plan by ELETRONUCLEAR Paulo Carneiro Technical Advisor Technical Directorate.

Slide 1 NRC Perspectives on Reactor Safety Course Special Features of BWR Severe Accident Mitigation and Progression L. J. Ott Oak Ridge National Laboratory.

FUKUSHIMA RESPONSE George Attarian 1/21/2013. Fukushima Response Timeline: March 11: Event occurred March 18: INPO IER 11-1 issued (April 15) March 23:

Presented by: Muhammad Ayub Pakistan Nuclear Regulatory Authority Safety Enhancement at Nuclear Power Plants in Pakistan Prospects of Nuclear Energy in.

Vermont Yankee Presentation to VSNAP 7/17/13 VY/Entergy Fukushima Response Update Bernard Buteau.

Vermont Yankee Presentation to VSNAP 7/9/12 VY/Entergy Fukushima Response Bernard Buteau.

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.

ACADs (08-006) Covered Keywords Components, functions, operation, Auxiliary feedwater, Startup, hot standby, plant cooldown, emergency. Description Supporting.

Perspectives on the further safety enhancement of the NPPs with WWER reactors in response to Fukushima Daiichi accident Presented by SNRIU|SSTC NRS (Ukraine)

Status of ANS Standards Presented to NESCC 3/1/2011 Donald J. Spellman Vice Chair, ANS Standards Board.

Safety Features at KKNPP Insight of. Location: The Kudankulam is located on the coast of the Gulf of Mannar, at 25 kM to the north- east from Kanyakumari,in.

EUROTRANS - Helium cooled EFIT Probabilistic assessment of different DHR designs Karlsruhe, November Sophie EHSTER, Laurent VINCON.

“ Hard work and concern for the society is the key to success ” - O P Jindal On-site and Off-site Emergency Plans Based on Integral Risk Management – Key.

Sea Fukushima Dai-Ichi: Status before the Earthquake Units 1, 2, and 3 operate at full power. Steam produced by water boiling in the reactor vessel flows.

TRAINING AND DRILLS. Training and Drills Ensure A comprehensive, coordinated, and documented program as an integral part of the emergency management program.

Source: NRC Flickr Gallery, Courtesy Entergy Nuclear UCS Backgrounder on Pilgrim’s January 27, 2015 Event February 3,

NUCLEAR SAFETY Barbora Svobodová Angličtina-odborná II.

Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/2 Design Geoff Vaughan University of Central Lancashire,

1 6 th Review Meeting of the Convention on Nuclear Safety SLOVENIA Country Group 3 24 March 2014, Vienna.

ROSATOM STATE ATOMIC ENERGY CORPORATION “ROSATOM”

SMR-160: A Walk-away Safe Small Modular Nuclear Reactor

© 2011 Westinghouse Electric Company LLC. All Rights Reserved.Westinghouse Non-Proprietary Class 3 Kate Jackson Senior Vice President, Research & Technology.

Fukushima Incident Preliminary Analysis, Consequences and Safety Status of Indian NPPs Part-1 Dr. S.K.Jain Chairman & Managing Director NPCIL & BHAVINI.

Overview of Conventional 2-loop PWR Simulator. PCTRAN Dr

State-of-the-Art Reactor Consequence Analyses (SOARCA)

Outcome of the EU Nuclear Safety Stress Tests Andrej Stritar Chairman, ENSREG.

What about Japan?. Unit 1 Unit 2 Unit 3 Unit 4 Unit 5 Unit 6.

Fukushima Dai-ichi - LinkLink. Boiling Water Reactor – Video LinkVideo Link.

Nuclear Thermal Hydraulic System Experiment

Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.

TACIS Project: R8.01/98 – TRANSLATION, EDITING AND DIFFUSION OF DOCUMENTS (Result Dissemination) Probabilistic Safety Analysis Technology (PSA) TACIS R3.1/91.

C O N T R A C T O R I N F O R M A T I O N E X C H A N G E LashCIE Presentation 1/98 1 Recent Accomplishments and Future Directions Dan Giessing U.S. Department.

Fukushima Lessons Learnt and Follow-up Activities of Rostechnadzor Alexey Ferapontov, Acting Chairman Second European Nuclear Safety Conference

March 11, 2011 to Present. Presentation Overview Reactor Design and FeaturesChronology of EventsCurrent Status of Each ReactorRecovery Actions Kashiwazaki-Kariwa.

C O N T R A C T O R I N F O R M A T I O N E X C H A N G E Reister CE Presentation 1/98 1 Program Elements and Related Activities Rich Reister U.S. Department.

"... To design the control system that effectively matches the plant requires an understanding of the plant rivaling that of the plant's designers, operators,

Nuclear Power. What Is Nuclear Power? Nuclear power is the use of nuclear reactions that release nuclear energy, which generates heat. The energy produced.

Breakout Session V: Mitigation Strategies for Beyond Design Basis External Events (NTTF Recommendation 4.2) Fukushima Regulatory Response Workshop April.

Safety of At-Reactor High-Density Storage of Fuel in Pools Steve Jones Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission International.

IAEA International Atomic Energy Agency Occupational Radiation Protection during High Exposure Operations Lecture 2-2 Lessons Learnt from Occupational.

MEHB 513 Introduction on nuclear technology assignment GROUP MEMBERS:ID: SEEH CHONG CHIN ME YEE QIAN WAHME TING DING PINGME LIM JIA YINGME

I Overview of EU-APR1400 II Design Concept of Safety Systems III

By Annick Carnino (former Director of IAEA Division of Nuclear Installations Safety) PIME, February , 2012.

A generation ahead by design SMR -160 An Unconditionally Safe Source of Pollution-Free Nuclear Energy for the Post-Fukushima Age 1 By Dr. Kris Singh Holtec.

1 Nuclear Power Technology Development Westinghouse View Kiev March 2012 Dr. Nick Shulyak AP1000® is a registered trademark in the United States of Westinghouse.

Enhancing Safety at America’s Nuclear Energy Facilities U.S. Industry’s Fukushima Response Joseph Pollock, Nuclear Energy Institute Christopher H. Mudrick,

Plant & Reactor Design Passive Reactor Core Cooling System

UNIVERSITI TENAGA NASIONAL MEHB513 Introduction to Nuclear Technology SEM /2015 Group Assignment Fukushima Daiichi Nuclear Accident GROUP MEMBERS:

Post-Fukushima Severe Accident Management Update Kim, Hyeong Taek KHNP- Central Research Institute July KINS Safety Analysis Symposium.

The March 2011 Earthquake and Tsunami in Japan: A Nuclear Perspective Mary Lou Dunzik-Gougar, PhD Associate Chair of Nuclear Engineering and Health Physics.

FLEX Mitigation Strategies Overview (Rec 4.2) Fukushima Regulatory Response Workshop April 5, 2012.

Generator Operation. Video of Generator synchronizing.

Research on Safety System Configuration of HPR1000

Spent Fuel Pool Instrumentation NRC Order EA

Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.

Mitigation of Beyond Design Basis Events (MBDBE) Rule Implementation

Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions

SONGS Past, Current, and Future State May 4, 2016

Moving Forward From Fukushima Near-Term Task Force EP Recommendations

Grid Stability and Safety Issues Associated With Nuclear Power Plants

Session Name: Lessons Learned from Mega Projects

Severe accident management at Paks NPP

Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.

New Regulatory Requirements in Japan

Presentation transcript:

1 BREI Conducted Comprehensive Independent Reviews of Passive Heat Removal Systems with Ejectors-Condensers Euratom DEEPSSI Project for the design and development of a passive steam generator emergency feedwater system for existing and future PWRs using advanced steam injectors Independent Review of the Russian Passive Heat Removal System with Ejector-Condenser (PAHRSEC) for Implementation in VVERs and Other Reactor Technologies Evaluation of PAHRSEC in combination with steam-driven Auxiliary Feedwater Pumps for diversity in decay heat removal in the event of an extended Station Blackout for new VVER TOI reactor design.

2 Passive Heat Removal System with Ejector-Condenser (PAHRSEC) 1.Steam Generator 4. Check Valve 2.Ejector-Condenser 5. Start-up Valve 3.Heat Exchanger 6. Start-up Tank

3 BREI Developed Numerous Low Cost Mitigation Strategies for Fukushima Events Developed numerous strategies for coping with extended loss of AC power using existing equipment, manual actions, on-site portable equipment, pre-staged off-site equipment, and off-site personnel support including:  Equipment type, design, and quantity  On-site equipment storage and protection from external hazards  Off-site regional equipment storage  Emergency preparedness and procedures/training/staffing Designed cost-effective post-Fukushima Spent Fuel Pool Level Instrumentation System with provisions for missile protection, seismicity, reliability, independence, power supply, accuracy, displays, and testing for implementation at operating plants.