Nuclear Power Plant Instrumentation and Control in MEXICO
|
|
|
- Margaret Lambert
- 8 years ago
- Views:
Transcription
1 25 th Meeting of the IAEA Technical Working Group on Nuclear Power Plant Instrumentation and Control (TWG -NPPIC) Nuclear Power Plant Instrumentation and Control in MEXICO Dr. Francisco Javier Ramírez-Jiménez May 27-29, 2015, IAEA, Vienna
2 25 th Meeting of the IAEA Technical Working Group on Nuclear Power Plant Instrumentation and Control (TWG -NPPIC) Introduction OUTLINE Main Projects Developments Recommendations May 27-29, 2015, IAEA, Vienna
3 INTRODUCTION Laguna Verde Nuclear Power Plant
4 TWO General Electric (GE) Boiling Water Reactors (BWR) UNIT 1 started in years old UNIT 2 started in years old MEAN POWER : 1.6 GW ( 2.6 % ) Total energy generated : GW hr (4.5 %) Mean efficiency in the last 12 years: 83.6 %
5 20 th Anniversary of U2
6 Location of the Nuclear Power plant
7 Laguna Verde Nuclear Power Plant
8 Two important activities of the Nuclear Power Plant: POWER UPRATING OF THE LVNPP From 1.4 GW to 1.6 GW LIFE EXTENSION OF THE LVNPP Assurance of the long term operation From 30 years to 60 years
9 The operator of the plant is the Federal Commission of Electricity, CFE, of MEXICO GOVERNMENTAL The National Institute for Nuclear Research, ININ, is an advisor that provides scientific and technical support to the plant.
10 Life Extension to 60 years MAIN PROJECTS Proactive Ageing Management for Long Term Operation of Laguna Verde Nuclear Power Plant, LVNPP. (IAEA TC) Dry Storage of used nuclear fuel Chemical cleaning OBJECTIVES: Focus: To increase the reliability To reduce the collective dose * Spare parts
11 Project IAEA-MEX 2017 Instrumentation & Control Proactive Ageing Management for Long Term Operation of Laguna Verde Nuclear Power Plant, LVNPP Design, selection, installation, calibration, maintenance, repair, and optimization of nuclear instrumentation Deal with the obsolescence of electronic instrumentation, and control systems. Deal with the upgrading or reinforcement of nuclear instrumentation.
12 I&C ISSUES THAT AFFECT THE LONG TERM OPPERATION - OBSOLESCENCE OF SOFTWARE AND HARDWARE Operating systems for computerized instruments Memories Microcontrollers Integrated circuits Complex systems -AGEING OF INSTRUMENTATION AND CONTROL COMPONENTS Cabling Capacitors Relays Transformers
13 Ageing Management of Specific Instrumentation and Control Systems of the LVNPP - several systems of the plant have been identified as possible fields of action for upgrading or reinforcement. - we focus in common problems encountered in I&C systems i.e. in the Starting Range Neutron Monitoring System, SRNMS
14 - Measurement of the neutron fluxes -Review of the instrumentation used in the Starting Range Neutron Monitoring System, SRNMS -Recomendations for the verification and inspection of the SRNMS in LVNPP -Grounding,shielding and protection of electronic equipments to reduce the electromagnetic interference and transients in nuclear instrumentation
15 DEVELOPMENTS Optimization of the Off Gas Radiation Monitoring System Instituto Nacional de Investigaciones Nucleares, March 2015 México
16 Improvements in the Radiation Monitoring System Ventilation of the Turbo Generator Building
17 Radiological Monitoring Network around the Nuclear Power Plant
18 Gamma radiation detector NUMAC Simulator for training Personal Computer based Simulator
19 Measurement of process variables Oxygen Hydrogen Conductivity
20 Upgrading and Refurbishment of electronic modules Booster Unit for the Turbo Pumps Electro-Hydraulic System, Turbo Pumps
21 Diagnostic of damaged circuits Transponder, Reactor Manual Control
22 SPECIAL RADIATION MEASUREMENTS Gamma-spectrometry in the vent sampling, TGB
23 Pool deep Exposure rate profile along the control rods, Unit 2
24 RECOMMENDATIONS Consider a training course on Wireless Technologies applications on NPPs in Add a worshop on aging management of I&C components in Look for more benefits for MS in: - Application of codes and standardscc., Application of diversity, independence and physical separation in different levels of I&C systems, 2017 Add a training course on the process performance optimization, including new radiation detectors technologies, and stressing the importance of full understanding of the processes, Add a training course on maintenance of digital I&Csystems in Add a training course on dedication of I&C systems and components in Consider a consultant meeting that includes also sellers of new I&C components for NPPs in Discuss the importance of right selection of participants in the propossed events (WS, TC mainly)
25 To promote the disemination of information about: - Operational experiences and solutions on common problems encountered in I&C systems of NPPs - Recommendations and Guidelines for best practices
Long Term Operation R&D to Investigate the Technical Basis for Life Extension and License Renewal Decisions
Long Term Operation R&D to Investigate the Technical Basis for Life Extension and License Renewal Decisions John Gaertner Technical Executive Electric Power Research Institute Charlotte, North Carolina,
Long term support solutions for Nuclear Instrumentation & Control
Long term support solutions for Nuclear Instrumentation & Control...ensuring the long-term safety and availability of your I&C systems. 02 LONG TERM SUPPORT SOLUTIONS Maintaining the safe and reliable
Introductions: Dr. Stephen P. Schultz
Introductions: Dr. Stephen P. Schultz Vienna, Austria 1 3 September 2015 Work Experience Current Member Advisory Committee on Reactor Safeguards, U.S. Nuclear Regulatory Commission, 12/2011 Chair, Fukushima
GE Energy. Reactor Instrumentation for the New Era of Nuclear Power
GE Energy Reactor Instrumentation for the New Era of Nuclear Power Pioneering nuclear energy GE has been a pioneer in the development of nuclear power since its infancy. From the first U.S. government
IAEA Research Reactor Operations & Maintenance Support 2014 TRTR Meeting August 3rd-7th, 2014 Benson Hotel Portland Oregon
IAEA Research Reactor Operations & Maintenance Support 2014 TRTR Meeting August 3rd-7th, 2014 Benson Hotel Portland Oregon By Charles R Morris Personal Nuclear History Contents 1. Introduction 2. Digital
Dynamic Behavior of BWR
Massachusetts Institute of Technology Department of Nuclear Science and Engineering 22.06 Engineering of Nuclear Systems Dynamic Behavior of BWR 1 The control system of the BWR controls the reactor pressure,
Levelized costs for nuclear, gas and coal for Electricity, under the Mexican scenario.
Levelized costs for nuclear, gas and coal for Electricity, under the Mexican scenario. Javier C. Palacios, Gustavo Alonso, Ramón Ramírez, Armando Gómez, Javier Ortiz, Luis C. Longoria. Instituto Nacional
Cyber Security Design Methodology for Nuclear Power Control & Protection Systems. By Majed Al Breiki Senior Instrumentation & Control Manager (ENEC)
Cyber Security Design Methodology for Nuclear Power Control & Protection Systems By Majed Al Breiki Senior Instrumentation & Control Manager (ENEC) 1. INTRODUCTION In today s world, cyber security is one
CONNECTING YOU TO SPECIALIST ELECTRICAL SUPPORT services
CONNECTING YOU TO SPECIALIST ELECTRICAL SUPPORT services SpecialistS IN ELECTRICAL SUPPORT SERVICES TO MINING, UTILITIES & industry Ampcontrol is committed to supporting our customers to maintain efficient
AN APPLICATION STUDY FOR THE CLASS IE DIGITAL CONTROL AND
- 39 - AN APPLICATION STUDY FOR THE CLASS IE DIGITAL CONTROL AND MONITORING SYSTEM m,,,.,.., HIROYUKIFUKUMITSU Nuclear Power Plant Department, EISC MITSUBISHI ELECTRIC CORPORATION Kobe, Japan XA9846493
FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS -
International Conference Nuclear Energy in Central Europe 2000 Golf Hotel, Bled, Slovenia, September 11-14, 2000 FIRE RISK ASSESSMENT IN GERMANY - PROCEDURE, DATA, RESULTS - H.P. Berg Bundesamt für Strahlenschutz
Technical Meeting on the Implications of the Fukushima Daiichi Accident on the Safety of Fuel Cycle Facilities. IAEA Headquarters Vienna, Austria
1 J7-TM-44883 Technical Meeting on the Implications of the Fukushima Daiichi Accident on the Safety of Fuel Cycle Facilities IAEA Headquarters Vienna, Austria 1 5 July 2013 INFORMATION SHEET 1. Background
Fire Protection Program Of Chashma Nuclear Power Generating Station Pakistan Atomic Energy Commission 5/28/2015 1
Fire Protection Program Of Chashma Nuclear Power Generating Station Pakistan Atomic Energy Commission 5/28/2015 1 Nuclear Power in Pakistan Nuclear Power Plants Capacity (MWe) Year of Commissioning In
Application of FPGA-based Safety Controller for Implementation of NPPs I&C Systems Vladimir Sklyar, Technical Director
Application of FPGA-based Safety Controller for Implementation of NPPs I&C Systems Vladimir Sklyar, Technical Director Seminar FPGA-based I&C Systems in Nuclear Applications February 4, 2015, Energiforsk,
NUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER
NUCLEARINSTALLATIONSAFETYTRAININGSUPPORTGROUP DISCLAIMER Theinformationcontainedinthisdocumentcannotbechangedormodifiedinanywayand shouldserveonlythepurposeofpromotingexchangeofexperience,knowledgedissemination
TRAINING SOFTWARE FOR SAFEGUARDS AT FUEL FABRICATION PLANTS
TRAINING SOFTWARE FOR SAFEGUARDS AT FUEL FABRICATION PLANTS Na Young Lee 1), Byung Marn Koh 1), Susan Pickett 2) 1) Korea Institute of Nuclear Non-proliferation and Control 2) International Atomic Energy
LATIN AMERICAN NETWORK FOR EDUCATION AND TRAINING IN NUCLEAR TECHNOLOGY LANENT R. Barrachina, J.L. François
IAEA Technical Meeting on networking for nuclear education 5-8 December 2011, Vienna, Austria LATIN AMERICAN NETWORK FOR EDUCATION AND IN NUCLEAR TECHNOLOGY LANENT R. Barrachina, J.L. François Created
Alternatives of Financing for New Nuclear Reactors in Mexico
IAEA-CN-164-2S07 Alternatives of Financing for New Nuclear Reactors in Mexico Gustavo Alonso, Javier C. Palacios, Jose R. Ramirez, Luis C. Longoria, Edmundo del Valle* Instituto Nacional de Investigaciones
Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]
![Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]](/thumbs/22/1436302.jpg "Published in the Official State Gazette (BOE) number 166 of July 10th 2009 [1]")
Nuclear Safety Council Instruction number IS-22, of July 1st 2009, on safety requirements for the management of ageing and long-term operation of nuclear power plants Published in the Official State Gazette
RADIATION MONITORING SYSTEMS
RADIATION MONITORING SYSTEMS Area monitors Process monitors In-line, Adjacent-to-Line monitors Local/remote processors, Data Acquisition Systems NUPIC Certified, NRC Approved Vendor Wide Range Sensitivity
IAEA INTERNATIONAL FACT FINDING EXPERT MISSION OF THE NUCLEAR ACCIDENT FOLLOWING THE GREAT EAST JAPAN EARTHQUAKE AND TSUNAMI
IAEA INTERNATIONAL FACT FINDING EXPERT MISSION OF THE NUCLEAR ACCIDENT FOLLOWING THE GREAT EAST JAPAN EARTHQUAKE AND TSUNAMI Tokyo, Fukushima Dai-ichi NPP, Fukushima Dai-ni NPP and Tokai NPP, Japan 24
Improving reactor safety systems using component redundancy allocation technique
NUKLEONIKA 2005;50(3):105 112 ORIGINAL PAPER Improving reactor safety systems using component redundancy allocation technique Aziz Shafik Habib, Hoda Abd-el Monem Ashry, Amgad Mohamed Shokr, Azza Ibrahim
Status on Spanish Regulations and Industry. actions related to Filtered Containment. Venting Systems (FCVS)
Status on Spanish Regulations and Industry actions related to Filtered Containment Venting Systems (FCVS) Sara González Systems Engineering Department Consejo de Seguridad Nuclear, Spain Technical Meeting
TRANSFORMERS AFTERMARKET SPARES, SERVICE & REPAIR
TRANSFORMERS SPARES, SERVICE & REPAIR 02 TRANSFORMERS ENERGY SOLUTIONS FOR THE GLOBAL POWER INDUSTRY BRUSH Transformers is globally renowned for the quality of its products, innovation and service. Our
Nuclear power plant systems, structures and components and their safety classification. 1 General 3. 2 Safety classes 3. 3 Classification criteria 3
GUIDE 26 June 2000 YVL 2.1 Nuclear power plant systems, structures and components and their safety classification 1 General 3 2 Safety classes 3 3 Classification criteria 3 4 Assigning systems to safety
Technical support for nuclear power operations
IAEA-TECDOC-1078 Technical support for nuclear power operations INTERNATIONAL ATOMIC ENERGY AGENCY April 1999 The IAEA does not normally maintain stocks of reports in this series. However, copies of these
Nuclear Energy: Nuclear Energy
Introduction Nuclear : Nuclear As we discussed in the last activity, energy is released when isotopes decay. This energy can either be in the form of electromagnetic radiation or the kinetic energy of
Accidents of loss of flow for the ETTR-2 reactor: deterministic analysis
NUKLEONIKA 2000;45(4):229 233 ORIGINAL PAPER Accidents of loss of flow for the ETTR-2 reactor: deterministic analysis Ahmed Mohammed El-Messiry Abstract The main objective for reactor safety is to keep
Management of delayed nuclear power plant projects
IAEA-TECDOC-1110 Management of delayed nuclear power plant projects INTERNATIONAL ATOMIC ENERGY AGENCY The IAEA does not normally maintain stocks of reports in this series. However, electronic copies The
RENCEE SAFETY MARIES
IAEA MINISTE ERIAL CONFE RENCEE ON NUCLEAR SAFETY Vienna,, 20 24 June 2011 CHAIRPERSONS SUMM MARIES 1 The attached texts are the Chairpersons summaries of the main proposals that emerged from the Working
At the request of CFE s Area of Electric Systems Programming
Network Analysis Electric Systems Expansion and Operation Planning Transmission Pricing Services At the request of CFE s Area of Electric Systems Programming (Gerencia de Programación de Sistemas Eléctricos,
IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS
IMPLEMENTATION OF A MANAGEMENT SYSTEM FOR OPERATING ORGANIZATIONS OF RESEARCH REACTORS Eduardo Kibrit 1, Afonso Rodrigues de Aquino 2 and Désirée Moraes Zouain 3 1 Centro Tecnológico da Marinha em São
Cyber Security and the Canadian Nuclear Industry a Canadian Regulatory Perspective
Cyber Security and the Canadian Nuclear Industry a Canadian Regulatory Perspective Terry Jamieson Vice-President Technical Support Branch Canadian Nuclear Safety Commission August 11, 2015 www.nuclearsafety.gc.ca
I&C Status in France & Recommendations to IAEA
I&C Status in France & Recommendations to IAEA IAEA TWG-NPPIC Meeting 22-24 May 2013 Vienna Patrick SALAUN EDF R&D Contents 1. I&C projects at EDF NPPs The 900 MW series 3 rd Ten-Yearly Outage 4 th Ten-Yearly
UTILIZING RESEARCH REACTORS FOR EDUCATION AND TRAINING: INTERNET REACTOR LABORATORY
UTILIZING RESEARCH REACTORS FOR EDUCATION AND TRAINING: INTERNET REACTOR LABORATORY Judy VYSHNIAUSKAS Junior Professional Officer Research Reactor Section Division of Nuclear Fuel Cycle and Waste Technology
TENDER FOR TECHNICAL BUILDING MAINTENANCE SERVICES TERMS OF REFERENCE. April 2013 OVERALL PURPOSE
ANNEX 3 EUROPEAN UNION DELEGATION TO GEORGIA ADMINISTRATION TENDER FOR TECHNICAL BUILDING MAINTENANCE SERVICES TERMS OF REFERENCE April 2013 OVERALL PURPOSE Offices of the EU Delegation The Contractor
From Soviet Atomic Project to Leadership in Education and Research Worldwide
National Research Nuclear University MEPhI Enhancement of the Competitiveness among the World Leading Education and Research Centres From Soviet Atomic Project to Leadership in Education and Research Worldwide
Advanced Safeguards Measurement, Monitoring and Modelling Laboratory (AS3ML) at JRC-ITU-Ispra
Advanced Safeguards Measurement, Monitoring and Modelling Laboratory (AS3ML) at JRC-ITU-Ispra IAEA Safeguards Symposium Vienna, October 21, 2014 Willem JANSSENS, Paolo PEERANI, Claudio BERGONZI, Erik WOLFART,
Poznan University of Technology Faculty of Electrical Engineering
Poznan University of Technology Faculty of Electrical Engineering Contact Person: Pawel Kolwicz Vice-Dean Faculty of Electrical Engineering pawel.kolwicz@put.poznan.pl List of Modules Academic Year: 2015/16
Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT
Report WENRA Safety Reference Levels for Existing Reactors - UPDATE IN RELATION TO LESSONS LEARNED FROM TEPCO FUKUSHIMA DAI-ICHI ACCIDENT 24 th September 2014 Table of Content WENRA Safety Reference Levels
of Nuclear Power I COVER STORY
COVER STORY of Nuclear Power I t may seem odd to our U.S. audience that GE would dedicate an issue of ORBIT to an industry that in 1979 saw U.S. new power plant construction come to a standstill. However,
July 30, 2012 Nuclear Emergency Response Headquarters Government-TEPCO Med-and-long Term Response Council
Supplementary Document 1 Research and Development Road Map for Decommissioning Units 1 4 at TEPCO's Fukushima Daiichi Nuclear Power Plant July 30, 2012 Nuclear Emergency Response Headquarters Government-TEPCO
FPGA- based technology and systems for I&C of existing and advanced reactors
International Conference on Opportunities and Challenges for Water Cooled Reactors in the 21st Century Vienna, Austria, 27 30 October 2009 FPGA- based technology and systems for I&C of existing and advanced
Technical Meeting on Evaluation and Dependability Assessment of Software for Safety Instrumentation and Control Systems at Nuclear Power Plants
Technical Meeting on Evaluation and Dependability Assessment of Software for Safety Instrumentation and Control Systems at Nuclear Power Plants Hosted by the Government of the Republic of Korea through
Training in Emergency Preparedness and Response
Working to Protect People, Society and the Environment Training in Emergency Preparedness and Response Nuclear Safety and Security Programme Nuclear Safety and Security Programme Training in Emergency
Stack Monitor Operating Experience Review
INL/CON-09-15233 PREPRINT Stack Monitor Operating Experience Review 23rd Symposium on Fusion Engineering L. C. Cadwallader S. A. Bruyere May 2009 This is a preprint of a paper intended for publication
Portuguese Health Physics Society: Calibrating Pen Dosimeters with and without a Phantom
Portuguese Health Physics Society: Calibrating Pen Dosimeters with and without a Phantom Fernanda B. C. Nonato, Claudinei T. Cescon and Linda V. E. Caldas, Instituto de Pesquisas Energéticas e Nucleares,
ELECTRICAL AND COMPUTER ENGINEERING By Joan Omoruyi, Engineering Librarian, Northeastern University
ELECTRICAL AND COMPUTER ENGINEERING By Joan Omoruyi, Engineering Librarian, Northeastern University. Soon after physicists began to understand electricity, the electrical engineering profession was born
ELECTRICAL AND I&C EQUIPMENT OF A NUCLEAR FACILITY
ELECTRICAL AND I&C EQUIPMENT OF A NUCLEAR FACILITY 1 Introduction 5 2 Scope of application 6 3 Requirement specification, selection, and procurement of electrical and I&C equipment and cables 7 3.1 General
RC-17. Alejandro V. Nader National Regulatory Authority Montevideo - Uruguay
RC-17 Radiation Protection in Waste Management and Disposal Implementing the Joint Convention on the Safety of Spent Fuel Management and on the Safety of Radioactive Waste Management Alejandro V. Nader
Mexican Efforts Towards Building a Design Basis Threat for Radiological and Nuclear Environment.
Mexican Efforts Towards Building a Design Basis Threat for Radiological and Nuclear Environment. Juan Eibenschutz H./ José Luis Delgado/ Carina Martínez International Regulators Conference on Nuclear Security.
PIONEER ROBOT TESTING PROGRAM AND STATUS
PIONEER ROBOT TESTING PROGRAM AND STATUS Joseph N. Herndon and Dennis C. Haley Robotics and Process Systems Division Oak Ridge National Laboratory P.O. Box 2008 Oak Ridge, Tennessee 37831-6305 (865) 574-7065
International Symposium on Nuclear Security
International Symposium on Nuclear Security The Nuclear Security actions taken in Mexico to get an effective protection system of nuclear and radioactive facilities RUBÉN RAMÍREZ GUERRERO rramirezg@cnsns.gob.mx
Power transformers. Generator step-up and system intertie power transformers Securing high-quality AC transmission
Power transformers Generator step-up and system intertie power transformers Securing high-quality AC transmission Generator step-up transformers Built to withstand continuous full load Generator step-up
Long term operation integrated processes for delivering extended asset performance
Long term operation integrated processes for delivering extended asset performance 15 04 2015 Agenda 1. Introduction 2. Long term operation process for delivery 3. Business planning and key assumptions
Alstom Grid Services. Transformer lifecycle management GRID
Alstom Grid Services Transformer lifecycle management GRID Transformer services A COMPLETE RANGE OF SOLUTIONS As a critical component of networks, the power transformer is essential to high voltage electrical
Elements Elements describe the essential outcomes. 1. Prepare to diagnose and repair air conditioning and HVAC system
AURETU004 Application Competency Field Unit Sector Elements Elements describe the essential outcomes. 1. Prepare to diagnose and repair air conditioning and HVAC system 2. Diagnose air conditioning and
IAEA-TECDOC-1402 Management of life cycle and ageing at nuclear power plants: Improved I&C maintenance
IAEA-TECDOC-1402 Management of life cycle and ageing at nuclear power plants: Improved I&C maintenance Report prepared within the framework of the Technical Working Group on Nuclear Power Plant Control
SafePoint RMS. Sustainable Committed Secure. SafePoint. Monitoring Solutions
SafePoint RMS Sustainable Committed Secure SafePoint SafePoint Radiation Monitoring Solutions Nuclear Measurements Business Unit of AREVA www.canberra.com SafePoint RMS Radiation Monitoring Solutions Nuclear
NORTH CAROLINA EASTERN MUNICIPAL POWER AGENCY SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1. Renewed License No. NPF-63
CAROLINA POWER & LIGHT COMPANY NORTH CAROLINA EASTERN MUNICIPAL POWER AGENCY DOCKET NO. 50-400 SHEARON HARRIS NUCLEAR POWER PLANT, UNIT 1 RENEWED FACILITY OPERATING LICENSE 1. The Nuclear Regulatory Commission
Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team
IAEA TM on Source Term Evaluation for Severe Accidents, Vienna, 21-23 October 2013 Source Term Determination Methods of the Slovenian Nuclear Safety Administration Emergency Response Team Tomaž Nemec Slovenian
Turbo generators Best quality for thermal power plants
Turbo generators Best quality for thermal power plants www.andritz.com ANDRITZ HYDRO Turbo generators International technology Group ANDRITZ is a globally leading supplier of plants, equipment, and services
Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2
Operating Performance: Accident Management: Severe Accident Management Programs for Nuclear Reactors REGDOC-2.3.2 September 2013 Accident Management: Severe Accident Regulatory Document REGDOC-2.3.2 Canadian
PROJECT REVIEW COMMITTEE MEETING Project 628801 - PRNM and ARTS/MELLLA
PROJECT REVIEW COMMITTEE MEETING Project 628801 - PRNM and ARTS/MELLLA Jim Snyder, Presenter Jim Snyder, Project Manager Nishant Chadha, System Engineer Dave Brown, Project Sponsor July xx, 2012 Statement
Optimization of Digital Industrial Radiography (DIR) Techniques for Specific Applications: An IAEA Coordinated Research Project
IV Conferencia Panamericana de END Buenos Aires Octubre 2007 Optimization of Digital Industrial Radiography (DIR) Techniques for Specific Applications: An IAEA Coordinated Research Project U. Ewert, U.
HYRADIX ALPHA 4 PERFORMANCE REVIEW
HYRADIX ALPHA 4 PERFORMANCE REVIEW TECHNICAL BULLETIN: TB-03-001 January 2004 The Center for Fuel Cell Research and Applications a program of the Houston Advanced Research Center www.harc.edu/fuelcell
Government Degree on the Safety of Nuclear Power Plants 717/2013
Translation from Finnish. Legally binding only in Finnish and Swedish. Ministry of Employment and the Economy, Finland Government Degree on the Safety of Nuclear Power Plants 717/2013 Chapter 1 Scope and
FACILITY AND VENUE PROTECTION
FACILITY AND VENUE PROTECTION INTRODUCTION In late 2001, the Department of Homeland Security was created to develop and coordinate the implementation of a comprehensive national strategy to secure the
Investigations of a Long-Distance 1000 MW Heat Transport System with APROS Simulation Software
th International Conference on Structural Mechanics in Reactor Technology (SMiRT ) Espoo, Finland, August 9-4, 9 SMiRT -Division 3, Paper 56 Investigations of a Long-Distance MW Heat Transport System with
Rev. 02. STD DEP T1 3.4-1 (Table 7.6-5 and Figures 7.6-1, 7.6-2, 7.6-4a) STD DEP 7.2-1 (Table 7.6-5 and Figures 7.6-1, 7.6-2)
7.6 All Other Instrumentation Systems Required for Safety The information in this section of the reference ABWR DCD, including all subsections, tables, and figures, is incorporated by reference with the
V K Raina. Reactor Group, BARC
Critical facility for AHWR and PHWRs V K Raina Reactor Group, BARC India has large reserves of Thorium Critical facility Utilisation of Thorium for power production is a thrust area of the Indian Nuclear
PROPOSALS FOR UNIVERSITY REACTORS OF A NEW GENERATION
PROPOSALS FOR UNIVERSITY REACTORS OF A NEW GENERATION Introduction R.P. Kuatbekov, O.A. Kravtsova, K.A. Nikel, N.V. Romanova, S.A. Sokolov, I.T. Tretiyakov, V.I. Trushkin (NIKIET, Moscow, Russia) Worldwide,
Spent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste
Spent Fuel Project Office Interim Staff Guidance - 17 Interim Storage of Greater Than Class C Waste Issue: Guidance is necessary on the interim storage of greater than Class C (GTCC) waste due to the revision
Emergency Power System Services Industrial UPS, Batteries, Chargers, Inverters and Static Switches
Emergency Power System Services Industrial UPS, Batteries, Chargers, Inverters and Static Switches Downtime Is Not An Option The industrial uninterruptible power supply (UPS) is the foundation of your
Development and Application of POSAFE-Q PLC Platform
Development and Application of POSAFE-Q PLC Platform MyeongKyun Lee a, SeungWhan Song a, DongHwa Yun a a POSCO ICT Co. R&D center, Korea Techno-complex 126-16, 5-ka, Anam-dong, Sungbuk, Seoul, Republic
BAR-CODE BASED WEIGHT MEASUREMENT STATION FOR PHYSICAL INVENTORY TAKING OF PLUTONIUM OXIDE CONTAINERS
BNL-66301 BAR-CODE BASED WEIGHT MEASUREMENT STATION FOR PHYSICAL INVENTORY TAKING OF PLUTONIUM OXIDE CONTAINERS AT THE MINING AND CHEMICAL COMBINE RADIOCHEMICAL REPROCESSING PLANT NEAR KRASNOYARSK, SIBERIA.
Study Plan. MASTER IN (Energy Management) (Thesis Track)
Plan 2005 T Study Plan MASTER IN (Energy Management) (Thesis Track) A. General Rules and Conditions: 1. This plan conforms to the regulations of the general frame of the programs of graduate studies. 2.
Critical Review of the Swedish Stress Tests Report
1 Critical Review of the Swedish Stress Tests Report Oda Becker September 2012 1 Introduction... 2 2 Weaknesses the Swedish Stress Test Described... 3 2.1 Earthquake... 3 2.2 Flooding... 4 2.3 Extreme
Atlas Copco Construction Technique Service. Extended Warranty and Service Agreements The peace of mind you need to focus on your business
Atlas Copco Construction Technique Service Extended Warranty and Service Agreements The peace of mind you need to focus on your business Atlas Copco Construction Technique Service Extended Warranty and
NEI 06-13A [Revision 0] Template for an Industry Training Program Description
![NEI 06-13A [Revision 0] Template for an Industry Training Program Description](/thumbs/30/14663734.jpg "NEI 06-13A [Revision 0] Template for an Industry Training Program Description")
NEI 06-13A [Revision 0] Template for an Industry Training Program Description NEI 06-13A [Revision 0] Nuclear Energy Institute Template for an Industry Training Program Description ACKNOWLEDGEMENTS This
NUCLEAR SERVICES & TECHNOLOGY
The Most Important Substance You ve Never Heard Of (Probably) The story of Molybdenum-99 Michael Washer, PE, Merrick and Company Martin Biggs, Chief Engineer, Phoenix Engineering NUCLEAR SERVICES & TECHNOLOGY
EQUIPMENT QUALIFICATION
Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Assessment and Engineering Aspects Important to Safety 12 23 October 2015 Trieste, Italy Ales KARASEK INTRODUCTION Ales Karasek I&C
Code of Conduct on the Safety and Security of Radioactive Sources
FOREWORD In recent years there has been a growing awareness of the potential for accidents involving radiation sources, some such accidents having had serious, even fatal, consequences. More recently still,
A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS
A MTR FUEL ELEMENT FLOW DISTRIBUTION MEASUREMENT PRELIMINARY RESULTS W. M. Torres, P. E. Umbehaun, D. A. Andrade and J. A. B. Souza Centro de Engenharia Nuclear Instituto de Pesquisas Energéticas e Nucleares
Office for Nuclear Regulation
ONR GUIDE CONTAINMENT: CHEMICAL PLANTS Document Type: Nuclear Safety Technical Assessment Guide Unique Document ID and Revision No: NS-TAST-GD-021 Revision 2 Date Issued: March 2013 Review Date: March
February 19, 2014. Senior Fellow, Nuclear Energy Systems & Services Division Power Systems Company
JAPAN-U.S. DECOMISSIONING AND REMEDIATION FUKUSHIMA RECOVERY FORUM February 19, 2014 Senior Fellow, Nuclear Energy Systems & Services Division Power Systems Company Toshiba global formation Information
Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants
Nuclear Safety Council Instruction number IS- 23 on in-service inspection at nuclear power plants Published in the Official State Gazette (BOE) No 283 of November 24 th 2009 Nuclear Safety Council Instruction
ABB Dedicated Products, Systems and Services for the Power Generation Industry
ABB Dedicated Products, Systems and Services for the Power Generation Industry ABB Now, More Than Ever, your Dependable and Focused Power Generation Partner It is estimated that the North American demand
centre for radiation protection
centre for radiation protection To excel in radiation science so as to: enforce and promote the radiation safety of workers, the public and the environment; ensure that irradiating apparatus and nuclear
What s It All About? The Sun as a Power Source Instructor Guide
What s It All About? The Sun as a Power Source Instructor Guide Subject Area Unit Grade Time Science Earth Science K - 1st grade 45 minutes Overview This activity reinforces the concept that the sun supplies
Nuclear Energy of Ukraine - History
Nuclear Energy of Ukraine - History 1950-s Uranium Industry was started 1962 Ministry of Energy and Electrification of Ukraine was established(ukraine a Republic of Soviet Union) 1965 Unique Energy System
TECHNICAL MEETING ON IN-PILE TESTING AND INSTRUMENTATION FOR DEVELOPMENT OF GENERATION-IV FUELS AND STRUCTURAL MATERIALS
651-T1-TM-42785 TECHNICAL MEETING ON IN-PILE TESTING AND INSTRUMENTATION FOR DEVELOPMENT OF GENERATION-IV FUELS AND STRUCTURAL MATERIALS I. BACKGROUND Halden, Norway 21 24 August 2012 INFORMATION SHEET
INTRODUCTION. Three Mile Island Unit 2
INTRODUCTION here was an accident at Three Mile Island Unit 2 on March 28,1979. It caused extensive damage to the plant's nuclear fuel core. Most of the plant's major systems were relatively undamaged.
Belgian Stress tests specifications Applicable to power reactors 17 May 2011
Belgian Stress tests specifications Applicable to power reactors 17 May 2011 Introduction Considering the accident at the Fukushima nuclear power plant in Japan, the European Council of March 24 th and
Holtec International. Multi-Purpose Canisters for Long-Term Interim Storage. June 17, 2015. Rick Springman, Ph.D. Director of International Projects
Holtec International Multi-Purpose Canisters for Long-Term Interim Storage June 17, 2015 Rick Springman, Ph.D. Director of International Projects Dry Storage & Transport Projects Wet Storage Projects 1
Chlorine Gas Detection System Operation & Maintenance
Chlorine Gas Detection System Operation & Maintenance Maynard King K&D Pratt Instrumentation 2011 Clean and Safe Drinking Water Workshop Chlorine Gas Detector Operation, Maintenance, Checks 1. Why you
Human Resource Management in Nuclear Safety
Human Resource Management in Nuclear Safety Christer Viktorsson Nuclear Installations Safety Role of the (IAEA) Established in 1957 143 Member States 2,200 staff Three Pillars: Safeguards Nuclear Technology
Announcement of a new IAEA Co-ordinated Research Programme (CRP)
Announcement of a new IAEA Co-ordinated Research Programme (CRP) 1. Title of Co-ordinated Research Programme Design and engineering aspects of the robustness of digital instrumentation and control (I&C)
Bonn Call-for-Action Joint Position Statement by the IAEA and WHO
Bonn Call-for-Action Joint Position Statement by the IAEA and WHO The International Atomic Energy Agency (IAEA) held the International Conference on Radiation Protection in Medicine: Setting the Scene
7.1 General 5 7.2 Events resulting in pressure increase 5
GUIDE YVL 2.4 / 24 Ma r ch 2006 Primary and secondary circuit pressure control at a nuclear power plant 1 Ge n e r a l 3 2 General design requirements 3 3 Pressure regulation 4 4 Overpressure protection