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

Slides:



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

Generic Pressurized Water Reactor (PWR): Safety Systems Overview
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Presented by: Muhammad Ayub Pakistan Nuclear Regulatory Authority Safety Enhancement at Nuclear Power Plants in Pakistan Prospects of Nuclear Energy in.
Safety Implications of the Fukushima Nuclear Accident Sheldon L. Trubatch, Ph.D., J.D. Vice-Chairman Arizona Section American Nuclear Society.
n.ogv
LFR plant assessment against a Fukushima-like scenario Technical Workshop to Review Safety and Design Aspects of European LFR Demonstrator (ALFRED), European.
Overview of Incident at Fukushima Daiich Nuclear Power Station (1F) (Informal personal observations) April 2011.
May 22nd & 23rd 2007 Stockholm EUROTRANS: WP 1.5 Task Containment Assessment IP-EUROTRANS DOMAIN 1 Design WP 1.5 Safety Assessment of the Transmutation.
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.
Nuclear Reactors. What is fission again? Nuclear reactors take advantage of the process of nuclear fission which splits an atom and releases a great deal.
EUROTRANS - Helium cooled EFIT Probabilistic assessment of different DHR designs Karlsruhe, November Sophie EHSTER, Laurent VINCON.
POWER PLANT.
Nuclear Power Station Lecture No 5. A generating station in which nuclear energy is converted into electrical energy is known as a Nuclear power station.
Main Requirements on Different Stages of the Licensing Process for New Nuclear Facilities Module 4.5/2 Design Geoff Vaughan University of Central Lancashire,
Energy for the Future Belene NPP Design Features May, 2008 Riviera Holiday Club, Varna, Bulgaria Jordan Georgiev BNPP Manager.
ROSATOM STATE ATOMIC ENERGY CORPORATION “ROSATOM”
Fukushima Incident Preliminary Analysis, Consequences and Safety Status of Indian NPPs Part-1 Dr. S.K.Jain Chairman & Managing Director NPCIL & BHAVINI.
SAFETY OBJECTIVES FOR GENERATION III NPP APPLIED TO EPR DESIGN OPTIONS PRESENTATION 26 – 29 September 2010, Nesebar, Bulgaria WATTELLE Emmanuel IRSN, France.
Overview of Conventional 2-loop PWR Simulator. PCTRAN Dr
Nuclear disaster 3 mile. History In 1979 at three mile nuclear power plant which is in the united states. A cooling malfunction caused part of the core.
Generation Aino Ahonen CABABILITY OF APROS IN THE ANALYSES OF DIESEL LOADING SEQUENCES E. Raiko, H.Kontio, K.Porkholm, presented by A. Ahonen.
ACADs (08-006) Covered Keywords Containment Isolation, actuation logic, Description Supporting Material
Deepwater Horizon Oil Spill On April 20, 2010, an explosion on the Deepwater Horizon MC252 drilling platform in the Gulf of Mexico caused the rig to sink.
Nuclear Energy Chapter 12. Nuclear Fuel Cycle Uranium mines and mills U-235 enrichment Fabrication of fuel assemblies Nuclear power plant Uranium tailings.
Fukushima Nuclear Disaster Team 07: Belsheim Joshua Francis Travis He Jiayang Moehling Anthony Ziemkowski Micah 1.
1 BREI Conducted Comprehensive Independent Reviews of Passive Heat Removal Systems with Ejectors-Condensers Euratom DEEPSSI Project for the design and.
Nuclear Thermal Hydraulic System Experiment
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions.
Long-term loss of all AC power supply sources for Belene NPP November 1, 2015 Reliability, Safety and Management Engineering and Software Development Services.
Nuclear Power Plant Meltdown Zach, Luke, and Nick.
March 11, 2011 to Present. Presentation Overview Reactor Design and FeaturesChronology of EventsCurrent Status of Each ReactorRecovery Actions Kashiwazaki-Kariwa.
Chapter 12 Nuclear Energy.
Fukushima Power Plant – Japan Post March 11, 2011
Agenda Background Update on Fukushima Daini Update on Fukushima Dai-ichi – Summary of Events at Fukushima Dai-ichi Summary of Radiation and Reports.
What can go wrong? Nuclear power plants cannot explode like a nuclear bomb. A bomb needs a critical mass in a confiuration which is not present in the.
Ta’Juan Dutrieuille November 4, 2009 Period 1
Nuclear Power Plant How A Nuclear Reactor Works.
Fukushima I nuclear accident, March 11, 2011 What happened, why and a better design.
Nuclear Power Plant How A Nuclear Reactor Works. Pressurized Water Reactor - Nuclear Power Plant.
THE FUKUSHIMA NUCLEAR ACCIDENT ON THE TECHNOLOGY DEVELOPMENT OF NEW NUCLEAR POWER PLANTS 1.IRSHAD NURHAKIM BIN NORAHIM (ME088151) 2.LEE SZE TENG (ME087909)
MEHB 513 Introduction on nuclear technology assignment GROUP MEMBERS:ID: SEEH CHONG CHIN ME YEE QIAN WAHME TING DING PINGME LIM JIA YINGME
LOW PRESSURE REACTORS. Muhammad Umair Bukhari
Plant & Reactor Design Passive Reactor Core Cooling System
Workshop on Risk informed decision making on nuclear power plant safety January 2011 SNRC, Kyiv, Ukraine Benefits and limitations of RIDM by Géza.
Japanese Nuclear Accident And U.S. Response April 20, 2011.
Nuclear power plant Performed by Zhuk A.D.. Purpose of this presentation is to show importance and danger of nuclear power plant. My opinion: I think.
Generator Operation. Video of Generator synchronizing.
BASIC PROFESSIONAL TRAINING COURSE Module XV In-plant accident management Case Studies Version 1.0, May 2015 This material was prepared by.
NuScale Generator A Practical Energy Alternative for the Future
Review Questions Chapter 5
Nuclear Power.
NUCLEAR ENERGY BY, P.PRAKRUTHI.KASHYAP Bsc II semester.
9.5 Nuclear Power Although nuclear power does not come from a fossil fuel, it is fueled by uranium, which is obtained from mining and is non-renewable.
Practical experience of the Russian VVER design organization in the use of PSA for verification of compliance with single and double failure criteria.
Ch. 10 Notes Day 1 5/25/16.
Nuclear Power.
Fukushima Daiichi Nuclear Plant Event Summary and FPL/DAEC Actions
Fukushima Lessons Learned
Federal Environmental, Industrial and Nuclear Supervision Service
Session Name: Lessons Learned from Mega Projects
Severe accident management at Paks NPP
IAEA International Conference on Topical Issues in Nuclear Installation Safety, 6-9 June, 2017 Investigation of performance of Passive heat removal system.
Fukushima Overview.
BASIC PROFESSIONAL TRAINING COURSE Module VII Probabilistic Safety Assessment Case Studies Version 1.0, July 2015 This material was prepared.
Japanese Nuclear Accident And U.S. Response
Approaches and measures aimed at ensuring safety, preventing severe accidents in new RF NPP designs Gutsalov N.A. 10/03/2016.
THE ROLE OF PASSIVE SYSTEMS IN ENHANCING SAFETY AND PREVENTING ACCIDENTS IN ADVANCED REACTORS Moustafa Aziz Nuclear and Radiological Regulatory Authority.
Nuclear power plant System Cost Safety
New Regulatory Requirements in Japan
Presentation transcript:

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

NEW RF NPP DESIGNS - VVER.1200 - VVER.TOI

An analysis of the events happened at the Fukushima-1 NPP An analysis of the events happened at the Fukushima-1 NPP shows that the accident was caused by a combination of extreme external influences. The main initiating events and subsequent failures were as follows: seismic impact with intensity above 8 points on the MSK scale; loss of normal and emergency (diesel generator) power supply (blackout); tsunami and, therefore, the ultimate heat sink failure (sea water); hydrogen generation due to zirconium-steam reaction, release of hydrogen in the reactor plant building volume and damage to the building due to hydrogen explosion; damage to the foundation of the reactor plant building and release of radioactivity into the environment; inability to recover the safety features for a long time.

protection against external hazards 20/400

passive safety systems The list of passive safety systems incorporated in the design includes the following ones: - a passive core flooding system from the ECCS hydro accumulators and from the system of second and third (low-pressure) stage hydro accumulators (HA-2,3); - a passive heat removal system (PHRS) from the steam generators with air-cooled heat exchangers-condensers located on the outer containment’s surface; - a system of passive hydrogen recombiners located in the containment volume. Autonomy (absence of core damage) is determined by the water inventory in the 2nd&3rd stage hydro accumulators and makes at least 24(72) h in case of the reactor coolant leak with break of the maximum diameter (DN=850) pipeline.

passive safety systems Passive heat removal system

additional (alternative) Safety systems For the case of NPP blackout and loss of all water ultimate heat sinks for more than 24(72) h, additional (alternative) systems are incorporated in the design. These additional systems include the following ones: - an alternative component cooling circuit. - an alternative diesel generator with air cooling;

additional (alternative) Safety systems

diesel-generator unit The diesel generator electric power output is 2 MW at 0.4 kV. The diesel-generator unit (DGU) is made in a container design that allows its outdoor storage and operation. The fuel inventory will in this case be sufficient to supply the DGU with fuel for about 20 days.

THANK YOU