Radioactive Materials from U.S. Nuclear Plants

Size: px
Start display at page:

Download "Radioactive Materials from U.S. Nuclear Plants"

Transcription

1 Routine Releases of Radioactive Materials from U.S. Nuclear Plants Dave Lochbaum Union of Concerned Scientists August 2014 Revision i 1 1

2 The idea for this material came during a November 2013 workshop on radiation monitoring conducted by the Bellefonte Efficiency & Sustainability Team (BEST) and the Mothers Against Tennessee River Radiation at (MATRR) in Chattanooga, TN (check out Thanks to Garry Morgan and Gretel Johnston of BEST/MATRR for reviewing drafts and providing very helpful feedback. 2

3 Background Boiling Water Reactors Pressurized Water Reactors Browns Ferry and Sequoyah (click on link to jump to topic or hit the space bar to advance to the next slide or the ESC button to exit the slideshow) 3

4 Parts of an Atom 4

5 Sources of Radioactive Materials FISSION BYPRODUCTS atoms split into two smaller atoms, and not always the same two smaller atoms; many of these fission byproduct atoms are unstable and seek stability ty by emitting radiation in the form of particles or energy waves FUEL CLADDING INTEGRITY fission byproducts are retained within fuel rod cladding, but only when cladding remains free of cracks and holes TRAMP URANIUM dust and flakes from uranium fuel pellets can adhere to the outside surface of fuel rod cladding and/or the fuel bundle hardware as tramp uranium 5

6 Sources of Radioactive Materials ACTIVATION PRODUCTS non-radioactive material can become activated t by interactions ti with radiation (e.g., get hit by neutrons or gamma rays) while flowing through the reactor core CHEMICAL INJECTION many plants inject chemicals into the feedwater that coat pipes to retard rusting and corrosion; some of these chemicals get activated RADIOLYTIC DISASSOCIATION water molecules flowing through the reactor core can get broken apart into hydrogen and oxygen molecules; subsequent interactions involving oxygen and nitrogen molecules l can form Carbon-14 RUST AND OTHER PARTICLES debris in the water can get activated flowing through the reactor core 6

7 Types of Radioactive Emissions ALPHA PARTICLES are the nuclei of helium atoms stripped of their electrons. Their large size allows the skin to stop them, but their size and energy level can severely damage whatever they hit. BETA PARTICLES are electrons. Their small size enables them to travel farther than alpha particles, but their relatively low energy levels allows aluminum foil, paper, and plastic lens to stop them. 7

8 Types of Radioactive Emissions GAMMA RAYS are photons emitted during nuclear transformations. Although having the same energy levels as beta particles, these energy waves require denser materials, like lead, to stop them. NEUTRONS are neutral subatomic particles. Possessing up to four times the energy levels of beta particles and gamma rays, it takes larger amounts of dense materials, like concrete, to stop them. 8

9 Timing of Radioactive Emissions HALF-LIFE is the time required for half an inventory of unstable atoms to emit radioactivity en route to stability. Half-lives range from small fractions of a second to many tens of thousands of years. Atom A Atom B Example: Half Life, years Atoms at 0 years Atoms after years Atoms after 0.50 years Atoms after 1.0 year ATOMS A AND B have 0.25 and 1.0 year half-lives, respectively. If they decay via emissions of the same type and energy level, which is more hazardous? It depends on the time context. Within a year, Atom A will have emitted 87.5% more radioactive bullets than Atom B. But Atom B will have 8 times more radioactive bullets to fire in its future than Atom A. 9

10 Types of Radioactive Waste HIGH-LEVEL WASTES from nuclear power plants are essentially the spent fuel. High-level wastes remain onsite in wet pools and/or in dry storage pending the opening of a federal repository for them. LOW-LEVEL WASTES from nuclear power plants are primarily the materials contaminated through contact with radioactively contaminated water. These materials include the fibrous filter elements and demineralizer resins used to process water and consumables (such as mop heads, shoe covers, wipes, etc.) used to protect against and cleanup water. Low-level wastes fall into three categories - Class A, B and C depending on the concentrations of radioactivity with Class C containing the highestlevels. Low-level wastes can be shipped to government licensed burial facilities for disposal. 10

11 Types of Radioactive Releases BATCH deliberate and planned (usually) discharges of radioactive material to the air (e.g., from the waste gas decay tank of a pressurized water reactor) or to the nearby lake, river, or ocean (e.g., from the floor drain sample tank of a boiling water reactor) BATCH PROCESS - tank to be discharged is mixed first to allow for more homogeneous blending of its contents, workers sample and analyze the contents to check against release limits, and contents are then discharged 11

12 Types of Radioactive Releases CONTINUOUS steady, routine discharge of radioactive material to the air (e.g., via offgas system of a boiling water reactor) or to the nearby lake, river, or ocean (e.g., from the cooling tower blowdown system of a boiling water reactor or pressurized water reactor) CONTINUOUS PROCESS radiation detectors monitor continuous flow pathways to sound alarm and perhaps p even automatically terminate the discharge when high radiation levels are discovered 12

13 What Causes Releases to Increase? Failed Fuel! Source: Areva presentation (ML12194A373) 13

14 Links to Applicable Regulations 10 CFR DOSE LIMITS FOR INDIVIDUAL MEMBERS OF THE PUBLIC APPENDIX A TO 10 CFR 50 GENERAL DESIGN CRITERIA FOR NUCLEAR POWER PLANTS (ESPECIALLY CRITERIA 60, 63, AND CFR 61 LICENSING REQUIREMENTS FOR LAND DISPOSAL OF RADIOACTIVE WASTE 14

15 Links to Other References REG GUIDE 4.1 RADIOLOGICAL ENVIRONMENTAL MONITORING FOR NUCLEAR POWER PLANTS STANDARD REVIEW PLAN (SRP) 11.2 LIQUID WASTE MANAGEMENT SYSTEM STANDARD REVIEW PLAN (SRP) 11.3 GASEOUS WASTE MANAGEMENT SYSTEM STANDARD REVIEW PLAN (SRP) 11.5 PROCESS AND EFFLUENT RADIOLOGICAL MONITORING INSTRUMENTATION AND SAMPLING SYSTEM Return to Main Menu 15

16 Routine Releases of Radioactive Materials: Boiling Water Reactors Liquid releases Gaseous releases Solid releases 16

17 17

18 Browns Ferry Fuel Performance Intact fuel rods preserve a barrier against discharge of fission byproducts to the environment. The Reactor Coolant System Activity performance indicator reflects fuel integrity the value increases when holes and cracks form in the metal walls of the fuel rods. 18

19 Browns Ferry Fuel Performance Results dating back to the year 2000 are online. 19

20 1.264 curies (1.42% of total liquid release) curies (98.58% of total liquid release) curies (0% of total liquid release) 44,043,000 liters (or 11,635,280 gallons) (i.e., scads of water) Source: TVA annual report 20 to NRC (ML14122A344)

21 Legend: Rarely radioactive Sometimes mildly radioactive Nearly always radioactive Drawing Source: TVA Browns Ferry Offsite Dose Calculation Manual, Rev. 21 (ML12123A018) 21

22 Browns Ferry Liquid Radwaste System Water leaked or spilled onto the floors as well as water used to clean components and areas is collected in the floor drain collector tanks. Water leaking from gaskets and seals that is collected in piping/tubing and carried to equipment drain sumps gets pumped to the waste collector tank. Water is treated, sometimes multiple times, before results from sample tanks show it is clean enough to be re-used or discharged to the river via the piping monitored by radiation monitor RM and volume recorded by flow indicator FI-77-60). 22

23 Browns Ferry Liquid Radwaste System Filters and resins are replaced when differential pressure across components or downstream chemistry indicates they have reached end of life. They are disposed of as solid waste. Drawing Source: TVA Browns Ferry Offsite Dose Calculation 23 Manual, Rev. 21 (ML12123A018)

24 Browns Ferry Reactor Building Equipment Drain Sump (right) 24

25 Browns Ferry Radwaste Tanks 25

26 Browns Ferry Liquid Radwaste System Water gets treated via filtration and demineralization to remove unwanted materials. Filteration uses fibrous cartridges to remove debris (e.g., rust flakes, cigarette butts, etc.) from the water. Used cartridges are disposed of as solid waste. Demineralizers use resin beads to remove dissolved materials (copper, salts, etc.) from the water. Used resin beads are either regenerated or disposed of as solid waste. 26

27 Browns Ferry Radwaste Resin Bags About the size and shape of sand, but way more expensive. Return to BWR Menu 27

28 curies (0.0015% of total gaseous release) curies (0.0135% of total gaseous release) curies (88.53% of total gaseous release) curies (11.45% of total gaseous release) Source: TVA annual report to NRC (ML14122A344) 28

29 Three Categories of Gaseous Releases 1) Elevated releases: discharges through the tall stack that t afford maximum mixing i of the gases being released curies of tritium released in 2013 (5.32% of total tritium gaseous release) 2) Ground-level releases: discharges from building vents that afford minimal mixing of the gases being released curies of tritium released in 2013 (14.42% of total tritium gaseous release) 3) Mixed mode releases: discharges from building vents but propelled upward by exhaust fans to provide moderate mixing of the gases being released curies of tritium released in 2013 (80.26% of total tritium gaseous release) 29

30 Browns Ferry Major Systems 30

31 15.23 curies of tritium released in 2013 (5.32% of total tritium gaseous release) Browns Ferry Gaseous Radwaste System (also called the Offgas System) This text box intentionally blank (until I typed in it) The Steam Jet Air Ejectors (SJAEs) pull air from the main condenser. Hydrogen (H 2 ) and oxygen molecules l are recombined and converted back to water. The remaining i gas and particles takes hours to flow through long, large-diameter piping before passing through charcoal filters and being discharged. Drawing Source: TVA Browns Ferry Offsite Dose Calculation Manual, Rev. 21 (ML12123A018) 31

32 Browns Ferry Offgas System Used during normal reactor operation curies of tritium released in 2013 (5.32% of total tritium gaseous release) Used during shutdowns and when power is no higher than 5 percent. Shutdown and low power p path includes less holdup and no adsorbers/filters. 32

33 229.8 curies of tritium released in 2013 (80.26% of total tritium gaseous release) An accident signal shuts down the normal ventilation systems and closes inlet and outlet dampers. The Standby Gas Treatment System (SGTS) starts to filter releases from the reactor building curies of tritium released at ground level in 2013 (14.42% of total tritium gaseous release) Drawing Source: TVA Browns Ferry Offsite Dose Calculation Manual, Rev. 21 (ML12123A018) 33

34 Turbine buildings with exhaust ducts/fans on roof Offgas exhaust stack Reactor buildings with exhaust ducts/fans on roof Return to BWR Menu 34

35 Return to Main Menu Return to BWR Menu Source: TVA annual report 35 to NRC (ML14122A344)

36 Routine Releases of Radioactive Materials: Pressurized Water Reactors Liquid releases Gaseous releases Solid releases 36

37 Offgas stack (see Alabama) Containment domes Turbine buildings with exhaust ducts/fans on roof 37

38 Sequoyah Fuel Performance Intact fuel rods preserve a barrier against discharge of fission byproducts to the environment. The Reactor Coolant System Activity performance indicator reflects fuel integrity the value increases when holes and cracks form in the metal walls of the fuel rods. 38

39 Sequoyah Fuel Performance Results dating back to the year 2000 are online. 39

40 curies (0% of total liquid release) 1,571 curies (100% of total liquid release) curies (0% of total liquid release) 882,700, liters (or 233,191,686 gallons) (i.e., scads of water) Source: TVA annual report to NRC (ML14118A380) 40

41 Sequoyah Liquid Radwaste System Drawing Source: TVA Sequoyah Offsite Dose Calculation Manual, Rev. 21 (ML13126A173) 41

42 Sequoyah Liquid Release Pathways Continuous release pathways Batch release pathway Continuous release pathway Drawing Source: TVA Sequoyah Offsite Dose Calculation Manual, Rev. 21 (ML13126A173) 42

43 Sequoyah Liquid Radwaste System Water leaked or spilled onto the floors as well as water used to wash down components and areas is collected in the floor drain collector tanks. Water leaking from gaskets and seals that is collected in piping/tubing pp gand carried to equipment drain sumps gets pumped to the waste collector tank. Water is treated, sometimes multiple times, before results from sample tanks show it is clean enough to be re-used (condensate storage tank) or discharged (via line monitored by RM ). Return to PWR Menu 43

44 53.82 curies (23.31% of total gaseous release) 0 curies (0% of total gaseous release) 0 curies (0% of total gaseous release) curies (74.78% of total gaseous release) 4.41 curies (1.91% of total gaseous release) ALL gaseous releases considered ground-level Source: TVA annual report 44 to NRC (ML14118A380)

45 Sequoyah Airborne Release Pathways Drawing Source: TVA Sequoyah Offsite Dose Calculation Manual, Rev. 21 (ML13126A173) Return to PWR Menu 45

46 46

47 Return to Main Menu Return to PWR Menu 47

48 48

49 Nearly one-quarter of a billion gallons of radioactively contaminated water in 2013 Return to Main Menu 49

LOCATION. Three Mile Island, in the Susquehanna River, Londonderry Township, Dauphin County, about 10 miles south of Harrisburg, Pennsylvania.

LOCATION. Three Mile Island, in the Susquehanna River, Londonderry Township, Dauphin County, about 10 miles south of Harrisburg, Pennsylvania. LOCATION Three Mile Island, in the Susquehanna River, Londonderry Township, Dauphin County, about 10 miles south of Harrisburg, Pennsylvania. FACILITIES TMI Nuclear Unit 1, with a capacity of about 800

More information

Nuclear Reactors. 3 Unit Nuclear Power Station - Coastal Bryon Nuclear Plant, Illinois. 3 Unit Nuclear Power Station - Desert

Nuclear Reactors. 3 Unit Nuclear Power Station - Coastal Bryon Nuclear Plant, Illinois. 3 Unit Nuclear Power Station - Desert 3 Unit Nuclear Power Station - Desert Nuclear Reactors Homeland Security Course February 1, 2007 Tom Gesell 3 Unit Nuclear Power Station - Coastal Bryon Nuclear Plant, Illinois 1 Power Reactor Statistics

More information

Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems

Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems Safety Review Models on Radioactive Source Term Design For PWR Waste Treatment Systems Xu Mingxia Waste Management Division, Nuclear Safety center, State Environmental Protection Administration, Beijing

More information

UNIT-5 NUCLEAR POWER PLANT. Joining of light nuclei Is not a chain reaction. Cannot be controlled

UNIT-5 NUCLEAR POWER PLANT. Joining of light nuclei Is not a chain reaction. Cannot be controlled UNIT-5 NUCLEAR POWER PLANT Introduction Nuclear Energy: Nuclear energy is the energy trapped inside each atom. Heavy atoms are unstable and undergo nuclear reactions. Nuclear reactions are of two types

More information

AP1000 European 11. Radioactive Waste Management Design Control Document

AP1000 European 11. Radioactive Waste Management Design Control Document 11.2 Liquid Waste Management Systems The liquid waste management systems include the systems that may be used to process and dispose of liquids containing radioactive material. These include the following:

More information

VVER-440/213 - The reactor core

VVER-440/213 - The reactor core VVER-440/213 - The reactor core The fuel of the reactor is uranium dioxide (UO2), which is compacted to cylindrical pellets of about 9 height and 7.6 mm diameter. In the centreline of the pellets there

More information

Chapter 2 Radiological Aspects of PWR Systems

Chapter 2 Radiological Aspects of PWR Systems Chapter 2 Radiological Aspects of PWR Systems 2.1 Overview Light water reactors are characterized by the fact that water serves as both the coolant and moderator. Two major types of reactors dominate the

More information

PRESENTATION OF NUCLEAR APPLICATIONS OF CONDENSATE TREATMENT

PRESENTATION OF NUCLEAR APPLICATIONS OF CONDENSATE TREATMENT Via Pietro Nenni, 15-27058 VOGHERA ITALY Tel. +39 0383 3371 Fax +39 0383 369052 E-mail: info@idreco.com PRESENTATION OF NUCLEAR APPLICATIONS OF CONDENSATE TREATMENT 0. MAIN CONDENSATE TREATMENT 1. REACTOR

More information

May 3, Dr. William J. Travers Executive Director for Operations Nuclear Regulatory Commission Washington, DC

May 3, Dr. William J. Travers Executive Director for Operations Nuclear Regulatory Commission Washington, DC Dr. William J. Travers Executive Director for Operations Nuclear Regulatory Commission Washington, DC 20555-0001 May 3, 2000 SUBJECT: HATCH NUCLEAR PLANT PETITION PURSUANT TO 10 CFR 2.206; REQUEST FOR

More information

The Fukushima Daiichi Incident

The Fukushima Daiichi Incident The data and information contained herein are provided solely for informational purposes. None of the information or data is intended by AREVA to be a representation or a warranty of any kind, expressed

More information

Nuclear Energy 101. The American Nuclear Society. Credit: W. D. Pointer, Ph. D. ANS Congressional Seminar Series

Nuclear Energy 101. The American Nuclear Society. Credit: W. D. Pointer, Ph. D. ANS Congressional Seminar Series Nuclear Energy 101 1 The American Nuclear Society Credit: W. D. Pointer, Ph. D Shippingport Reactor Vessel 3 We re going to wrestle with some big questions 4 We re going to wrestle with some big questions

More information

NUCLEAR ENERGY. Prepared by Engr. JP Timola Reference: Nuclear Energy by Dr. Lana Aref

NUCLEAR ENERGY. Prepared by Engr. JP Timola Reference: Nuclear Energy by Dr. Lana Aref NUCLEAR ENERGY Prepared by Engr. JP Timola Reference: Nuclear Energy by Dr. Lana Aref How is Nuclear Energy Produced? Nuclear energy is produced when an atom's nucleus is split into smaller nuclei by the

More information

EVPP 111 Lecture Dr. Largen

EVPP 111 Lecture Dr. Largen 1 Energy: Nuclear Energy EVPP 111 Lecture Dr. Largen 2 Outline s 3 Fig. 11.1a 4 Outline s 5 Energy: Nuclear Energy 4/26/86 series of explosions in one of reactors at plant blew roof (1102 ton) off reactor

More information

Nuclear Energy 101. The American Nuclear Society. Credit: W. D. Pointer, Ph. D. ANS Congressional Seminar Series

Nuclear Energy 101. The American Nuclear Society. Credit: W. D. Pointer, Ph. D. ANS Congressional Seminar Series Nuclear Energy 101 1 The American Nuclear Society Credit: W. D. Pointer, Ph. D Shippingport Reactor Vessel 3 We re going to wrestle with some big questions 4 We re going to wrestle with some big questions

More information

Exel(5n. Nuclear Plant Effluent and Radiological Environmental Monitoring Programs

Exel(5n. Nuclear Plant Effluent and Radiological Environmental Monitoring Programs Exel(5n. Plant Effluent and Radiological Environmental Monitoring Programs Exehtn. Two Programs,/ Radioactive Effluents Program o Measures releases of radioactivity from the station and calculates dose

More information

WHAT HAPPENED, WHAT IS GOING ON IN FUKUSHIMA NO.1 NUCLEAR POWER STATION?

WHAT HAPPENED, WHAT IS GOING ON IN FUKUSHIMA NO.1 NUCLEAR POWER STATION? WHAT HAPPENED, WHAT IS GOING ON IN FUKUSHIMA NO.1 NUCLEAR POWER STATION? Yoichiro Shimazu Research Institute of Nuclear Engineering University of Fukui WHERE IS FUKUSHIMA NUCLEAR POWER STATION? Sapporo

More information

Statement of Interest

Statement of Interest July 10, 2012 R. William Borchardt, Executive Director U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: PETITION TO REDRESS TECHNICAL SPECIFICATION DEFICIENCIES REGARDING IRRADIATED

More information

Nuclear Energy Revision Sheet

Nuclear Energy Revision Sheet Nuclear Energy Revision Sheet Question I Identify the NPP parts by writing the number of the correct power plant part in the blank. Select your answers from the list provided below. 1 Reactor 2 Steam generator

More information

Science of Nuclear Energy and Radiation. Nuclear Reactor Concepts. by Dr. Jerry M. Cuttler, PEng

Science of Nuclear Energy and Radiation. Nuclear Reactor Concepts. by Dr. Jerry M. Cuttler, PEng Science of Nuclear Energy and Radiation Nuclear Reactor Concepts by Dr. Jerry M. Cuttler, PEng 1. Introduction When we speak of a nuclear reactor, we mean a system that employs the fission reaction - the

More information

Pressurized Water Reactors

Pressurized Water Reactors Pressurized Water Reactors Illustrations and information from http://en.wikipedia.org/wiki/pressurize d_water_reactor The Ikata Nuclear Power Plant is located on Shikoku island at Ikata-cho. Heavy vs.

More information

TIMELINE/SCHEDULE. * Pertains to Original Schedule. US Army Corps of Engineers

TIMELINE/SCHEDULE. * Pertains to Original Schedule. US Army Corps of Engineers TIMELINE/SCHEDULE 2014 2015 2016 2017 J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J J A S O N D J F M A M J J A S O N D 2018 J F M A M J J A S O N D 3/27/14 - Contract Award Environmental

More information

Nuclear Power Plant. Mini Study. Sample file

Nuclear Power Plant. Mini Study. Sample file Nuclear Power Plant Mini Study Created and designed by Debbie Martin Nuclear Power Plant Mini Study The Whole Word Publishing The Word, the whole Word and nothing but the Word." Copyright March 2011 by

More information

METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF

METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF METHODOLOGY FOR ENSURING THE INTEGRATION OF ALARA INTO THE DESIGN OF THE AP1000 TM REACTOR Erik Slobe slobeed@westinghouse.com Westinghouse Electric Company LLC 1000 Westinghouse Drive Cranberry Township,

More information

TOPIC: KNOWLEDGE: K1.01 [2.5/2.5]

TOPIC: KNOWLEDGE: K1.01 [2.5/2.5] KNOWLEDGE: K1.01 [2.5/2.5] P283 The transfer of heat from the reactor fuel pellets to the fuel cladding during normal plant operation is primarily accomplished via heat transfer. A. conduction B. convection

More information

Name Date Class. How do fuels provide energy? What are the three major fossil fuels? Why are fossil fuels considered nonrenewable resources?

Name Date Class. How do fuels provide energy? What are the three major fossil fuels? Why are fossil fuels considered nonrenewable resources? Chapter 12 Energy and Material Resources Section 1 Summary Fossil Fuels How do fuels provide energy? What are the three major fossil fuels? Why are fossil fuels considered nonrenewable resources? A fuel

More information

WELCOME SM-1 DECOMMISSIONING PROJECT

WELCOME SM-1 DECOMMISSIONING PROJECT WELCOME SM-1 DECOMMISSIONING PROJECT Schedule 6:30 PM - 7:30 PM Open House Meet and interact with USACE and Fort Belvoir personnel 7:30PM - 8:30 PM Formal Presentation Q/A Session Poster Availability Public

More information

The Nuclear Crisis in Japan

The Nuclear Crisis in Japan The Nuclear Crisis in Japan March 21, 2011 Daniel Okimoto Alan Hanson Kate Marvel The Fukushima Daiichi Incident 1. Plant Design 2. Accident Progression 3. Radiological releases 4. Spent fuel pools " Fukushima

More information

The Fukushima Daiichi Incident Dr. Matthias Braun - 16 November p.1

The Fukushima Daiichi Incident Dr. Matthias Braun - 16 November p.1 Dr. Matthias Braun - 16 November 2012 - p.1 The Fukushima Daiichi Incident 1. Plant Design 2. Accident Progression 3. Radiological releases 4. Spent fuel pools 5. Sources of Information Matthias Braun

More information

AP Environmental Science II. Unit 2-2: Alternative Energy

AP Environmental Science II. Unit 2-2: Alternative Energy NOTE/STUDY GUIDE: Unit 2-2, Alternative Energy AP Environmental Science II, Mr. Doc Miller, M.Ed. North Central High School Name: ID#: NORTH CENTRAL HIGH SCHOOL NOTE & STUDY GUIDE AP Environmental Science

More information

The Fukushima Daiichi Incident Dr. Matthias Braun - 19 May p.1

The Fukushima Daiichi Incident Dr. Matthias Braun - 19 May p.1 Dr. Matthias Braun - 19 May 2011 - p.1 The Fukushima Daiichi Incident 1. Plant Design 2. Accident Progression 3. Radiological releases 4. Spent fuel pools 5. Sources of Information Matthias Braun PEPA4-G,

More information

Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development

Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development Preliminary Lessons Learned from the Fukushima Daiichi Accident for Advanced Nuclear Power Plant Technology Development A. Introduction The IAEA Report on Reactor and Spent Fuel Safety in the Light of

More information

25fh DOE/NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCE

25fh DOE/NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCE 25fh DOE/NRC NUCLEAR AIR CLEANING AND TREATMENT CONFERENCE AIR PURGE APPLIED TO SUBSTANTIALLY MITIGATE STACK RELEASE LEVELS RESULTING FROM BWR FUEL LEAK Peter G. Dorosko, PE Carolina Power & Light Brunswick

More information

Fukushima Event PCTRAN Analysis. Dr. LI-Chi Cliff Po. Dr. LI-Chi Cliff Po. March 25, 2011

Fukushima Event PCTRAN Analysis. Dr. LI-Chi Cliff Po. Dr. LI-Chi Cliff Po. March 25, 2011 Fukushima Event PCTRAN Analysis Dr. LI-Chi Cliff Po Fukushima Event PCTRAN Analysis Dr. LI-Chi Cliff Po 1. Description of Event March 25, 2011 The earthquake caused instant loss of offsite power. The scale-9

More information

What has the ABWR done to reduce the potential for Integranular Stress Corrosion Cracking?

What has the ABWR done to reduce the potential for Integranular Stress Corrosion Cracking? B Appendix Frequently Asked Questions What has the ABWR done to reduce the potential for Integranular Stress Corrosion Cracking? Boiling Water Reactors (BWR) have been supplying commercial electric power

More information

Types of Nuclear Reactors. Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer

Types of Nuclear Reactors. Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer Types of Nuclear Reactors Dr. GUVEN Professor of Aerospace Engineering Nuclear Science and Technology Engineer Types of Reactors (Fuel) As far as the type of fuels are concerned, three types of reactors

More information

HTS HEAT SOURCES & HEAT TRANSFER PATHS

HTS HEAT SOURCES & HEAT TRANSFER PATHS Approval Issue Module 6 Course 233 - Reactor &: Auxiliaries - Module 6 - HTS Heat Sources HTS HEAT SOURCES & HEAT TRANSFER PATHS OBJECTIVES: Mter completing this module you will be able to: 6.1 For each

More information

CANDU Safety #14 - Loss of Heat Sink Dr. V.G. Snell Director Safety & Licensing

CANDU Safety #14 - Loss of Heat Sink Dr. V.G. Snell Director Safety & Licensing CANDU Safety #14 - Loss of Heat Sink Dr. V.G. Snell Director Safety & Licensing 24/05/01 CANDU Safety - #14 - Loss of Heat Sink.ppt Rev. 0 vgs 1 Steam and Feedwater System steam lines have isolation valves

More information

CONDENSATE-FEEDWATER-BOILER SYSTEM ON-LINE ANALYZERS. On-Line Analyzer Sample Point Alarm Points Comments

CONDENSATE-FEEDWATER-BOILER SYSTEM ON-LINE ANALYZERS. On-Line Analyzer Sample Point Alarm Points Comments CONDENSATE-FEEDWATER-BOILER SYSTEM ON-LINE ANALYZERS On-Line Analyzer Sample Point Alarm Points 1. L.P. Heaters 2. H.P. Heaters 3. Boilers Feedwater Low 9.3 High 9.5 Boilers Low 8.7 High 9.7 Feedwater

More information

UK Nuclear

UK Nuclear UK Nuclear Industry @NuclearInst www.nuclearinst.com Why Nuclear power? Nuclear power supplies around 11% of the world s electricity, with an average of around 21% in the UK There are currently over 430

More information

R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada

R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada NUCLEAR REACTOR STEAM GENERATION R.A. Chaplin Department of Chemical Engineering, University of New Brunswick, Canada Keywords: Steam Systems, Steam Generators, Heat Transfer, Water Circulation, Swelling

More information

CANDU Fundamentals. Table of Contents

CANDU Fundamentals. Table of Contents Table of Contents 1 OBJECTIVES... 1 1.1 COURSE OVERVIEW... 1 1.2 ATOMIC STRUCTURE... 1 1.3 RADIOACTIVITY SPONTANEOUS NUCLEAR PROCESSES... 1 1.4 NUCLEAR STABILITY AND INSTABILITY... 2 1.5 ACTIVITY... 2

More information

UKEPR Issue 05

UKEPR Issue 05 Title: PCER Sub-Chapter 6.1 Sources of radioactive materials Total number of pages: 16 Page No.: I / III Chapter Pilot: S. BOUHRIZI Name/Initials Date 06-08-2012 Approved for EDF by: T. MARECHAL Approved

More information

Lessons learned from ongoing decommissioning project of Fugen NPS

Lessons learned from ongoing decommissioning project of Fugen NPS Workshop on "Current and Emerging Methods for Optimizing Safety and Efficiency in Nuclear Decommissioning, Sarpsborg, Norway, 7th 9th February 2017 Lessons learned from ongoing decommissioning project

More information

THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011

THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY. Edwin Lyman Union of Concerned Scientists May 26, 2011 THE FUKUSHIMA ACCIDENT: IMPLICATIONS FOR NUCLEAR SAFETY Edwin Lyman Union of Concerned Scientists May 26, 2011 The accident: many unknowns Many of the details of the Fukushima Daiichi accident are still

More information

Westinghouse AP1000 Nuclear Power Plant

Westinghouse AP1000 Nuclear Power Plant Westinghouse Non-Proprietary Class 3 April 2011 Westinghouse AP1000 Nuclear Power Plant Coping with Station Blackout Westinghouse Non-Proprietary Class 3 April 2011 Westinghouse AP1000 Nuclear Power Plant

More information

BACKGROUNDER Office of Public Affairs Phone:

BACKGROUNDER Office of Public Affairs Phone: BACKGROUNDER Office of Public Affairs Phone: 301-415-8200 Email: opa.resource@nrc.gov Three Mile Island Accident The accident at the Three Mile Island Unit 2 (TMI-2) nuclear power plant near Middletown,

More information

July 29, 2011 R. William Borchardt, Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC

July 29, 2011 R. William Borchardt, Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC July 29, 2011 R. William Borchardt, Executive Director for Operations U.S. Nuclear Regulatory Commission Washington, DC 20555-0001 SUBJECT: Petition Pursuant to 10 CFR 2.206 Demand For Information Regarding

More information

Presentation Outline. Basic Reactor Physics and Boiling Water Design Sequence of Events Consequences and Mitigation Conclusions and Lessons Learned

Presentation Outline. Basic Reactor Physics and Boiling Water Design Sequence of Events Consequences and Mitigation Conclusions and Lessons Learned Response of the Fukushima Dai-ichi Nuclear Plant to the March 11, 2011 Earthquake in Japan Dr. George Flanagan Oak Ridge National Laboratory Presented to the EERI/NEC Meeting April 12, 2012 Presentation

More information

PRESENTATION OF CONDENSATE TREATMENT

PRESENTATION OF CONDENSATE TREATMENT Via Pietro Nenni, 15-27058 VOGHERA ITALY Tel. +39 0383 3371 Fax +39 0383 369052 E-mail: info@idreco.com PRESENTATION OF CONDENSATE TREATMENT THE CONDENSATE TREATMENT The absence of impurities in feed water

More information

Chemical Engineering 693R

Chemical Engineering 693R Chemical Engineering 693R Reactor Design and Analysis Lecture 11 Nuclear Safety Spiritual Thought 2 2 Kings 6:16 And he answered, Fear not: for they that be with us are more than they that be with them.

More information

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C November 2, 2015

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C November 2, 2015 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 2, 2015 Mr. David Lochbaum Director, Nuclear Safety Project Union of Concerned Scientists P.O. Box 15316 Chattanooga, TN

More information

Deconstructing the Nuclear Accident at the Fukushima-Daiichi Plant: What Went Wrong and What are the Prospects of Recovery?

Deconstructing the Nuclear Accident at the Fukushima-Daiichi Plant: What Went Wrong and What are the Prospects of Recovery? Deconstructing the Nuclear Accident at the Fukushima-Daiichi Plant: What Went Wrong and What are the Prospects of Recovery? Goldschmidt Conference 2011 Fukushima Review Session Prague, Czech Republic Edward

More information

Auxiliary Systems K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University

Auxiliary Systems K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Auxiliary Systems K.S. Rajan Professor, School of Chemical & Biotechnology SASTRA University Joint Initiative of IITs and IISc Funded by MHRD Page 1 of 6 Table of Contents 1 VENTILATION SYSTEM... 3 2 ANNULUS

More information

Plant Layout. Chapter Plant Layout and Arrangement 8-1

Plant Layout. Chapter Plant Layout and Arrangement 8-1 8 Chapter Plant Layout and Arrangement Plant Layout The ABWR Plant includes all buildings which are dedicated to housing systems and the equipment related to the nuclear system or controls access to this

More information

Unit 2: Electricity and Energy Resources

Unit 2: Electricity and Energy Resources 9 9 Table of Contents Unit 2: Electricity and Energy Resources Chapter 9: Energy Sources 9.1: Fossil Fuels 9.2: Nuclear Energy 9.3: Renewable Energy Sources Fossil Fuels 9.1 Using Energy You can see energy

More information

4/30/12. Chapter: Energy Sources

4/30/12. Chapter: Energy Sources Table of Contents Chapter: Energy Sources Section: Section : Section : Using Energy You can see energy being used in many ways, throughout the day. Furnaces and stoves use thermal energy to heat buildings

More information

Nuclear Safety in Light of Fukushima. Andrew C. Kadak, Ph.D. Council of State Governments June 19, 2012

Nuclear Safety in Light of Fukushima. Andrew C. Kadak, Ph.D. Council of State Governments June 19, 2012 Nuclear Safety in Light of Fukushima Andrew C. Kadak, Ph.D. Council of State Governments June 19, 2012 Background Former Professor of the Practice in the MIT Nuclear Science and Engineering Department

More information

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015

Joint ICTP-IAEA Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety. Trieste,12-23 October 2015 Joint ICTP- Essential Knowledge Workshop on Deterministic Safety Analysis and Engineering Aspects Important to Safety Trieste,12-23 October 2015 Safety classification of structures, systems and components

More information

KNFC Crud Sampling and Fuel Cleaning Technology Development

KNFC Crud Sampling and Fuel Cleaning Technology Development KNFC Crud Sampling and Fuel Cleaning Technology Development Park, J.Y. 1, Kwon, Y.B. 1, Shin, J.C. 1, Park, J.Y. 1, Choi, J.S. 1, Kim, Y.K. 1, Choi, K.S. 1, Choi, I.K. 2 1 Korea Nuclear Fuel Co., Ltd.,

More information

AP1000 European 9. Auxiliary Systems Design Control Document

AP1000 European 9. Auxiliary Systems Design Control Document 9.2 Water Systems 9.2.1 Service Water System The service water system (SWS) supplies cooling water to remove heat from the nonsafety-related component cooling water system (CCS) heat exchangers in the

More information

Nuclear Power Volume II - Nuclear Power Plants

Nuclear Power Volume II - Nuclear Power Plants PDHonline Course E338 (5 PDH) Nuclear Power Volume II - Nuclear Power Plants Instructor: Lee Layton, PE 2012 PDH Online PDH Center 5272 Meadow Estates Drive Fairfax, VA 22030-6658 Phone & Fax: 703-988-0088

More information

APPENDIX B, TABLE B.2.4 DISPOSITION OF NEI COMMENTS ON CHAPTER V OF GALL REPORT

APPENDIX B, TABLE B.2.4 DISPOSITION OF NEI COMMENTS ON CHAPTER V OF GALL REPORT APPENDIX B, TABLE B.2.4 DISPOSITION OF NEI COMMENTS ON CHAPTER V OF GALL REPORT This Page Intentionally Left Blank NUREG-1739 B.2.4-ii April 2001 April 2001 B.2.4-1 NUREG-1739 Table B.2.4: Disposition

More information

Lecture (3) on. Nuclear Reactors. By Dr. Emad M. Saad. Mechanical Engineering Dept. Faculty of Engineering. Fayoum University

Lecture (3) on. Nuclear Reactors. By Dr. Emad M. Saad. Mechanical Engineering Dept. Faculty of Engineering. Fayoum University 1 Lecture (3) on Nuclear Reactors By Dr. Emad M. Saad Mechanical Engineering Dept. Faculty of Engineering Fayoum University Faculty of Engineering Mechanical Engineering Dept. 2015-2016 2 Nuclear Fission

More information

Standardized RP Task Qualifications. Module

Standardized RP Task Qualifications. Module Page: 1 of 45 Standardized RP Task Module Standardized RP Task Date: 6/16/2017 4:04:48 PM LP Number: Standardized RP Task Page: 2 of 45 INITIATING DOCUMENTS None REQUIRED TOPICS None CONTENT REFERENCES

More information

An Overview of the ACR Design

An Overview of the ACR Design An Overview of the ACR Design By Stephen Yu, Director, ACR Development Project Presented to US Nuclear Regulatory Commission Office of Nuclear Reactor Regulation September 25, 2002 ACR Design The evolutionary

More information

Physics 171, Physics and Society Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1.

Physics 171, Physics and Society Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1. Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1. Maria is riding her bicycle on a flat road at 10 mi/hr. Then she squeezes the brakes and comes

More information

Prairie Island Nuclear Generating Plant. EAL Reference Manual. Revision 9

Prairie Island Nuclear Generating Plant. EAL Reference Manual. Revision 9 Prairie Island Nuclear Generating Plant EAL Reference Manual Notice to Users This document has been prepared for the Prairie Island Nuclear Generating Plant (PINGP). Its purpose is to provide general information

More information

Example Pressurized Water Reactor Defense-in-Depth Measures For GSI-191, PWR Sump Performance

Example Pressurized Water Reactor Defense-in-Depth Measures For GSI-191, PWR Sump Performance Example Pressurized Water Reactor Defense-in-Depth Measures For GSI-191, PWR Sump Performance ATTACHMENT Introduction This paper describes a range of defense-in-depth measures that either currently exist

More information

Overview of the NSIAC Initiative in the US for Buried and Underground Piping & Tanks

Overview of the NSIAC Initiative in the US for Buried and Underground Piping & Tanks Overview of the NSIAC Initiative in the US for Buried and Underground Piping & Tanks David Smith EPRI IAEA Technical Meeting on Ageing Management of Buried and Underground Piping and Tanks for NPPs October

More information

The 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations

The 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations The 2011 Tohoku Pacific Earthquake and Current Status of Nuclear Power Stations March 31, 2011 Tokyo Electric Power Company Tohoku Pacific Ocean Earthquake Time: 2:46 pm on Fri, March 11, 2011. Place:

More information

Physics 171, Physics and Society Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1.

Physics 171, Physics and Society Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1. Physics 171, Physics and Society Quiz 1 1pm Thurs Sept 14, 2017 Each question has one correct answer, or none (choose e on the clicker). 1. Maria is riding her bicycle on a flat road at 10 mi/hr. Then

More information

AP1000 European 19. Probabilistic Risk Assessment Design Control Document

AP1000 European 19. Probabilistic Risk Assessment Design Control Document 19.39 In-Vessel Retention of Molten Core Debris 19.39.1 Introduction In-vessel retention of molten core debris through water cooling of the external surface of the reactor vessel is a severe accident management

More information

F. BODIN 1, Ph. FOURNIER 1, L. MARTIN 2 1 COGEMA La Hague BEAUMONT HAGUE Cedex - France 2 SALVAREM BEAUMONT HAGUE Cedex - France

F. BODIN 1, Ph. FOURNIER 1, L. MARTIN 2 1 COGEMA La Hague BEAUMONT HAGUE Cedex - France 2 SALVAREM BEAUMONT HAGUE Cedex - France COGEMA EXPERIENCE ON DECONTAMINATION AND UNDERWATER AUTOMATICALLY REMOTE CUTTING USING ULTRA HIGH PRESSURE WATER DURING NUCLEAR DECOMMISSIONING OPERATIONS THE AQUARAD ROBOT F. BODIN 1, Ph. FOURNIER 1,

More information

Progress Status Classified by Countermeasures

Progress Status Classified by Countermeasures Progress Status Classified by :Progressed (Legend color changed) Legend Implemented Under construction Field work started, but construction not started Appendix 2 Field work not started yet Areas Issues

More information

Announcements. Homework 9 due on Tuesday.

Announcements. Homework 9 due on Tuesday. Thursday, November 29th. Announcements. Homework 9 due on Tuesday. Lecture #23-1 http://www.google.com/intl/en/press/pressrel/20071127_green.html Lecture #23-2 Lecture #23-3 Lecture #23-4 Lecture #23-5

More information

RADIOACTIVE WASTE MANAGEMENT AT CERNAVODA NPP AFTER 5 YEARS OF EXPERIENCE

RADIOACTIVE WASTE MANAGEMENT AT CERNAVODA NPP AFTER 5 YEARS OF EXPERIENCE International Conference Nuclear Energy for New Europe 2002 Kranjska Gora, Slovenia, September 9-12, 2002 www.drustvo-js.si/gora2002 RADIOACTIVE WASTE MANAGEMENT AT CERNAVODA NPP AFTER 5 YEARS OF EXPERIENCE

More information

AP1000 European 9. Auxiliary Systems Design Control Document

AP1000 European 9. Auxiliary Systems Design Control Document 9.3 Process Auxiliaries 9.3.1 Compressed and Instrument Air System The compressed and instrument air system (CAS) consists of three subsystems; instrument air, service air, and high-pressure air. Instrument

More information

Power Stations Nuclear power stations

Power Stations Nuclear power stations Power Stations Nuclear power stations Introduction A nuclear power plant is a thermal power station in which the heat source is a nuclear reactor. The heat is used to generate steam which drives a steam

More information

OUTLINE OF THE ROKKASHO MOX FUEL FABRICATION PLANT

OUTLINE OF THE ROKKASHO MOX FUEL FABRICATION PLANT OUTLINE OF THE ROKKASHO MOX FUEL FABRICATION PLANT Ikeda K., Deguchi M., Mishima T. Japan Nuclear Fuel Ltd., Rokkasho-mura, Aomori-ken 039-3212 Japan ABSTRACT: JNFL s MOX fuel fabrication plant (JMOX)

More information

6.0 ENGINEERED SAFETY FEATURES

6.0 ENGINEERED SAFETY FEATURES Engineered Safety Features Materials 6.0 ENGINEERED SAFETY FEATURES This chapter of the U.S. EPR Final Safety Analysis Report (FSAR) is incorporated by reference with supplements as identified in the following

More information

Mixtures in Industry

Mixtures in Industry 3.7 Mixtures in Industry Key Question: How are mixtures separated in industry? Many industries separate mixtures to make pure products. In this section, you will learn about three industries that separate

More information

Special Interest Station Updates

Special Interest Station Updates Special Interest Station Updates 2018, Q1 [Feb. 2, 2017]: On Friday, Feb. 2, 2018, during a commissioning test on Darlington Nuclear Unit 2, power supply transformer some electrical cables overheated and

More information

Reprocessing and Spent Nuclear Fuel Management at the Savannah River Site

Reprocessing and Spent Nuclear Fuel Management at the Savannah River Site Reprocessing and Spent Nuclear Fuel Management at the Savannah River Site Some of the terms used in this factsheet are defined in IEER s on-line glossary. Tens of thousands of tons of radioactive material

More information

Spent Nuclear Fuel, Low Level Radioactive Waste and Decommissioning

Spent Nuclear Fuel, Low Level Radioactive Waste and Decommissioning Spent Nuclear Fuel, Low Level Radioactive Waste and Decommissioning Vermont Legislature January 29, 2009 - Revised Montpelier, Vermont Presented by Bruce Lacy 1 Topics Spent Nuclear Fuel Low Level Radioactive

More information

Thursday: Group A Hands-On Experience #2 Hayes 105 Group B Radiometric Dating Hayes 109

Thursday: Group A Hands-On Experience #2 Hayes 105 Group B Radiometric Dating Hayes 109 The truth emerged as a result of telling what you know and people challenging it. - William Scranton, chairman, Governor s Energy Council (Pennsylvania) When I started walking and I looked down and I saw

More information

Technical Challenges Associated with Shutdown Risk when Licensing Advanced Light Water Reactors

Technical Challenges Associated with Shutdown Risk when Licensing Advanced Light Water Reactors Technical Challenges Associated with Shutdown Risk when Licensing Advanced Light Water Reactors Marie Pohida a1, Jeffrey Mitman a a United States Nuclear Regulatory Commission, Washington, DC, USA Abstract:

More information

MFN Docket No

MFN Docket No GE Hitachi Nuclear Energy Richard E. Kingston Vice President, ESBWR Licensing P.O. Box 780 M/C A-65 Wilmington, NC 28402-0780 USA T 910.675.6192 F 910.362.6192 rick.kingston@ge.com MFN 09-169 Docket No.

More information

NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012

NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012 NUCLEAR POWER NEW NUCLEAR POWER PLANTS IN 2012 AP1000 IN FEBRUARY 2012, THE FIRST NUCLEAR POWER PLANTS IN THE US IN 35 YEARS WERE LICENSCED TO BEGIN CONSTRUCTION. TWO WESTINGHOUSE AP1000 NUCEAR REACTOR

More information

AP1000 The PWR Revisited

AP1000 The PWR Revisited IAEA-CN-164-3S05 AP1000 The PWR Revisited Paolo Gaio Westinghouse Electric Company gaiop@westinghouse.com Abstract. For nearly two decades, Westinghouse has pursued an improved pressurized water reactor

More information

Nuclear energy - four months after Fukushima

Nuclear energy - four months after Fukushima Institut»Jožef Stefan«Odsek za reaktorsko tehniko Nuclear energy - four months after Fukushima Iztok Tiselj "Jožef Stefan Institute", Reactor Engineering Division & Chair of Nuclear Engineering, Faculty

More information

INVESTIGATION OF THE BUILDING LIQUID EFFLUENT PIPE WORK AS PART OF THE AGEING MANAGEMENT AT SAFARI-1

INVESTIGATION OF THE BUILDING LIQUID EFFLUENT PIPE WORK AS PART OF THE AGEING MANAGEMENT AT SAFARI-1 INVESTIGATION OF THE BUILDING LIQUID EFFLUENT PIPE WORK AS PART OF THE AGEING MANAGEMENT AT SAFARI-1 N.F. Khathi and J.C. Mostert SAFARI-1 South African Nuclear Energy Corporation (Necsa), P.O. Box 582,

More information

An accident could result in dangerous levels of radiation that could affect the health and safety of the public living near the nuclear power plant.

An accident could result in dangerous levels of radiation that could affect the health and safety of the public living near the nuclear power plant. INTRODUCTION The construction and operation of nuclear power plants are closely monitored and regulated by the Nuclear Regulatory Commission (NRC). The Federal Emergency Management Agency (FEMA) also regulates

More information

An accident could result in dangerous levels of radiation that could affect the health and safety of the public living near the nuclear power plant.

An accident could result in dangerous levels of radiation that could affect the health and safety of the public living near the nuclear power plant. INTRODUCTION The construction and operation of nuclear power plants are closely monitored and regulated by the Nuclear Regulatory Commission (NRC). The Federal Emergency Management Agency (FEMA) also regulates

More information

Summary of the ABWR Key Features. Chapter2 Plant Overview 2-1. Safety Enhancement

Summary of the ABWR Key Features. Chapter2 Plant Overview 2-1. Safety Enhancement Chapter2 Plant Overview The key design objectives for the ABWR were established during the development program. The key goals, all of which were achieved, are as follows: Design life of 60 years. Plant

More information

AP1000 European 15. Accident Analysis Design Control Document

AP1000 European 15. Accident Analysis Design Control Document 15.2 Decrease in Heat Removal by the Secondary System A number of transients and accidents that could result in a reduction of the capacity of the secondary system to remove heat generated in the reactor

More information

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant

More information

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level

Nuclear Power Plant Safety Basics. Construction Principles and Safety Features on the Nuclear Power Plant Level Nuclear Power Plant Safety Basics Construction Principles and Safety Features on the Nuclear Power Plant Level Safety of Nuclear Power Plants Overview of the Nuclear Safety Features on the Power Plant

More information

Concentration Averaging and Encapsulation Branch Technical Position, Revision 1

Concentration Averaging and Encapsulation Branch Technical Position, Revision 1 Concentration Averaging and Encapsulation Branch Technical Position, Revision 1 Volume 1 U.S. Nuclear Regulatory Commission Office of Nuclear Material Safety and Safeguards February 2015 Table of Contents

More information

Supplemental Treatment Hanford Immobilized Low Activity Waste Discussion National Academies of Sciences, Engineering, and Medicine

Supplemental Treatment Hanford Immobilized Low Activity Waste Discussion National Academies of Sciences, Engineering, and Medicine Supplemental Treatment Hanford Immobilized Low Activity Waste Discussion National Academies of Sciences, Engineering, and Medicine Alex Smith Washington State Department of Ecology March 1, 2018 Outline

More information

PRESSURIZED WATER REACTOR PRIMARY CHEMSITRY INITIATIVES AND IMPACT ON PLANT DOSE RATES ABSTRACT

PRESSURIZED WATER REACTOR PRIMARY CHEMSITRY INITIATIVES AND IMPACT ON PLANT DOSE RATES ABSTRACT PRESSURIZED WATER REACTOR PRIMARY CHEMSITRY INITIATIVES AND IMPACT ON PLANT DOSE RATES D. Perkins 1, C. Haas 2, D. Hussey 3 Electric Power Research Institute 3420 Hillview Avenue, Palo Alto, California

More information