The document discusses potential strategies for decommissioning the damaged Fukushima Daiichi nuclear power plant reactors and spent fuel pools, referred to as "Plan-B Liquidation Strategies". It notes that dismantling the damaged reactors will be extremely challenging due to the harsh radiation environment. Leaving the reactors and spent fuel pools as they are is proposed as one option, but it would require public and regulatory approval.
An analysis of the Fukushima Nuclear Power PlantsRaja Mitra
The Fukushima Daiichi nuclear power plant in Japan suffered major damage from an earthquake and tsunami in March 2011. Six boiling water reactors were affected. The natural disasters caused a station blackout which prevented cooling of the reactor cores. This led to core damage in some reactors. In response, operators took mitigating actions like injecting seawater and borated water into the reactors and containments. The events prompted evacuations and emergency response. Lessons from Fukushima informed evaluations and enhancements to emergency preparedness at Florida Power and Light and their Duane Arnold Energy Center.
Zion Station RV Segmentation Presentation 37 pgsGary Krautwurst
This condensed 37 page presentation shows some of the steps of the processes involved in removing & segmenting the Reactor Vessel Internals - RVI (Core Barrel, Core Shroud, Baffle Plates, etc.) as well as the Reactor Vessel Segmentation - RVS performed by the Siempelkamp RV Segmentation Crew during the Decommissioning of the Zion Nuclear Power Station during 2014 - 2015.
Nuclear power plants have several advantages including needing less space, being well-suited to meet large power demands, having reliable operation, and not being affected by adverse conditions. They also have disadvantages such as high capital costs, risks of radioactivity, inability to operate at variable loads, and high maintenance costs. The essential components of a nuclear reactor are the reactor core, reflector, control mechanism, moderator, coolant, and shielding. The document then provides details on various types of nuclear reactors including pressurized water reactors, boiling water reactors, CANDU reactors, fast breeders, and gas cooled reactors.
The Current Status And Future Of Nuclear Power CJoe Miller
As of 2004, nuclear power provided 6.5% of the world's energy and 15.7% of the world's electricity, with the U.S., France, and Japan accounting for 57% of nuclear generated electricity. There are currently 439 nuclear power reactors operating in 31 countries. The U.S. reactor fleet is dominated by two reactor types: pressurized water reactors and boiling water reactors. Several advanced nuclear reactor designs are currently under review by the NRC, including the AP1000, ESBWR, US-APWR, and EPR. Factors both positively and negatively influence prospects for constructing new nuclear plants in the U.S.
This document provides an overview of the Advanced Boiling Water Reactor (ABWR) including key reactor specifications and design features. The ABWR has a thermal power rating of 3926 MWt and uses 872 fuel bundles in a 10x10 configuration. It has 205 fine motion control rod drives and 10 internal reactor pumps. The document describes the reactor pressure vessel, core internals, and standard fuel designs that can be used. It highlights improved safety features of the ABWR compared to previous boiling water reactor designs.
The document summarizes the Fukushima Daiichi nuclear power plant incident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, and risks to the spent fuel pools. The earthquake caused a station blackout which led to a loss of cooling and partial meltdowns in reactors 1, 2, and 3 over subsequent days. Hydrogen explosions damaged some buildings but the reinforced concrete containment structures remained intact. Offsite releases were limited but led to short term evacuations within 20 km.
An analysis of the Fukushima Nuclear Power PlantsRaja Mitra
The Fukushima Daiichi nuclear power plant in Japan suffered major damage from an earthquake and tsunami in March 2011. Six boiling water reactors were affected. The natural disasters caused a station blackout which prevented cooling of the reactor cores. This led to core damage in some reactors. In response, operators took mitigating actions like injecting seawater and borated water into the reactors and containments. The events prompted evacuations and emergency response. Lessons from Fukushima informed evaluations and enhancements to emergency preparedness at Florida Power and Light and their Duane Arnold Energy Center.
Zion Station RV Segmentation Presentation 37 pgsGary Krautwurst
This condensed 37 page presentation shows some of the steps of the processes involved in removing & segmenting the Reactor Vessel Internals - RVI (Core Barrel, Core Shroud, Baffle Plates, etc.) as well as the Reactor Vessel Segmentation - RVS performed by the Siempelkamp RV Segmentation Crew during the Decommissioning of the Zion Nuclear Power Station during 2014 - 2015.
Nuclear power plants have several advantages including needing less space, being well-suited to meet large power demands, having reliable operation, and not being affected by adverse conditions. They also have disadvantages such as high capital costs, risks of radioactivity, inability to operate at variable loads, and high maintenance costs. The essential components of a nuclear reactor are the reactor core, reflector, control mechanism, moderator, coolant, and shielding. The document then provides details on various types of nuclear reactors including pressurized water reactors, boiling water reactors, CANDU reactors, fast breeders, and gas cooled reactors.
The Current Status And Future Of Nuclear Power CJoe Miller
As of 2004, nuclear power provided 6.5% of the world's energy and 15.7% of the world's electricity, with the U.S., France, and Japan accounting for 57% of nuclear generated electricity. There are currently 439 nuclear power reactors operating in 31 countries. The U.S. reactor fleet is dominated by two reactor types: pressurized water reactors and boiling water reactors. Several advanced nuclear reactor designs are currently under review by the NRC, including the AP1000, ESBWR, US-APWR, and EPR. Factors both positively and negatively influence prospects for constructing new nuclear plants in the U.S.
This document provides an overview of the Advanced Boiling Water Reactor (ABWR) including key reactor specifications and design features. The ABWR has a thermal power rating of 3926 MWt and uses 872 fuel bundles in a 10x10 configuration. It has 205 fine motion control rod drives and 10 internal reactor pumps. The document describes the reactor pressure vessel, core internals, and standard fuel designs that can be used. It highlights improved safety features of the ABWR compared to previous boiling water reactor designs.
The document summarizes the Fukushima Daiichi nuclear power plant incident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, and risks to the spent fuel pools. The earthquake caused a station blackout which led to a loss of cooling and partial meltdowns in reactors 1, 2, and 3 over subsequent days. Hydrogen explosions damaged some buildings but the reinforced concrete containment structures remained intact. Offsite releases were limited but led to short term evacuations within 20 km.
The document summarizes the Fukushima Daiichi nuclear power plant accident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, risks to spent fuel pools, and sources of information on the incident. The earthquake caused a station blackout when the tsunami disabled backup diesel generators, leading to a loss of cooling and partial meltdowns in three reactor cores over several days before cooling was restored. Hydrogen explosions damaged some buildings housing the reactors.
The document summarizes the Fukushima Daiichi nuclear power plant accident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, risks to spent fuel pools, and sources of information on the incident. The earthquake caused a station blackout when the tsunami disabled backup diesel generators, leading to a loss of cooling and partial meltdowns in three reactor cores over several days before cooling was restored. Hydrogen explosions damaged some buildings housing the reactors.
The document summarizes the Fukushima Daiichi nuclear power plant incident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, and risks to the spent fuel pools. The earthquake caused a station blackout which led to a loss of cooling and partial meltdowns in reactors 1, 2, and 3 over subsequent days. Hydrogen explosions damaged some buildings but the reinforced concrete containment structures remained intact. Offsite releases were limited but led to short term evacuations within 20 km.
Fukushima Daiichi Nuclear Power Station Accident April19 2011Joe Miller
This document provides an overview of the Fukushima Daiichi nuclear accident that occurred in 2011 following an earthquake and tsunami in Japan. It discusses the plant designs, accident progression, spent fuel pools, radiological releases, and impact on US reactors. Key events included the loss of off-site power and emergency diesel generators due to flooding, melting of reactor cores due to lack of cooling, hydrogen explosions, and venting of radioactive gases. Lessons learned included enhancing backup cooling capabilities and emergency procedures for extreme events.
The document provides basic design information about BWR3 and BWR4 reactors, which are the types used at the Fukushima Daiichi nuclear power plant. It describes the Mark I containment system, typical reactor vessel configurations, and the reactor core isolation cooling system. It then summarizes the events at Fukushima Daiichi following the 2011 earthquake and tsunami, including loss of cooling, hydrogen explosions, fuel damage in reactors 1-3, and challenges with spent fuel pools.
The document discusses both internal and external factors that will influence the future development of nuclear power. Internally, factors like nuclear accidents, reactor designs, waste disposal, and public perceptions of radiation hazards will be important. Externally, energy demand, limitations on fossil fuels, concerns about climate change, and the feasibility of renewable energy will also impact prospects. However, there are still large uncertainties, and expanding nuclear power faces potential difficulties related to the pace of construction, uranium resources, waste issues, proliferation risks, and ensuring safety.
1. The document summarizes a project to inspect GE90 engines on Boeing 777 aircraft operated by Emirates due to issues with the stage 1 high pressure turbine shrouds. The author planned and oversaw inspections and engine removals to implement a permanent modification.
2. As maintenance planning officer, the author's role was to minimize operational impacts through precise planning of the monthly inspection schedule and engine removals in coordination with other departments. Technical knowledge of the engines and inspection process was required.
3. Through careful analysis of inspection findings and coordination between teams, the author was able to identify deterioration trends and schedule engine removals to implement modifications before any incidents occurred, closing the inspection requirement.
IRJET- Analysis of Cooling Fluid Interaction and Force Generated in a Pis...IRJET Journal
This document discusses analysis of cooling fluid interaction and force generated in a piston cylinder assembly. It begins with an abstract that outlines the goal of analyzing cooling fluid effects and cavitation in internal combustion engines using simulation. It then provides background on cavitation phenomena and stages. It describes the operation of internal combustion diesel engines, including the four strokes and cooling system. Equations are presented for forces on piston cylinder components under various assumptions. The document aims to simulate cavitation effects on cylinder liners and identify methods to increase engine component life.
The Hallam Nuclear Power Facility in Lancaster County, Nebraska was a former nuclear reactor that operated from 1962 to 1964. It was decommissioned and dismantled in the late 1960s, with some low-level radioactive materials entombed onsite. Current activities involve annual groundwater monitoring to ensure the stability of the entombed reactor. The site is 7.3 hectares and estimated costs for long-term stewardship activities from 1998 to past 2070 are $46,000 annually on average. The primary long-term activity is groundwater monitoring to ensure no contamination has migrated from the buried materials.
The document provides an overview of AEP's Mountaineer Commercial Scale Carbon Capture & Storage (CCS II) Project Phase I and lessons learned. Key points include: (1) The project aimed to demonstrate Alstom's Chilled Ammonia Process CO2 capture technology and deep saline CO2 storage at commercial scale. (2) Technical challenges included integrating the capture system with the existing power plant and variable coal supply, and managing water from the capture process. (3) Lessons involved selection of anhydrous ammonia as the reagent, exhaust stack options, water management approaches, steam sourcing for the capture system, and using variable speed pumping for CO2 compression and injection.
This document discusses the Fukushima Daiichi nuclear disaster in March 2011 in Japan. It provides details on:
1. How the earthquake and subsequent tsunami damaged the plant's cooling systems, leading to reactor meltdowns. The tsunami overwhelmed sea walls and flooded backup diesel generators.
2. How the loss of cooling led to a rise in pressure that opened steam relief valves, lowering water levels in reactor vessels. This exposed nuclear fuel and caused melting. Hydrogen explosions also occurred.
3. How radioactive materials were released into the environment after containment venting and other failures, spreading contamination. The accident progression highlights vulnerabilities from natural disasters and issues with the plant's design and emergency response.
ESS-Bilbao Initiative Workshop. Overview of cryo-modules for proton acceleratorsESS BILBAO
The document provides an overview of cryomodule design for proton accelerators. Cryomodule design is optimized based on factors like the accelerated particle properties, beam energy requirements, and operating mode (pulsed or CW). Two main cryomodule concepts are discussed - the TESLA cryostring concept, which integrates many cavities and magnets into long cryomodule units to maximize efficiency, and the SNS concept of independent, replaceable cryomodule units. The TESLA design rationale aims for high filling factor, moderate costs, effective alignment, and reproducible assembly. Consequences include integrating the cryomodule and cryogenic distribution to minimize thermal losses and employing long cryomodule strings supplied by a central cryogenic
Liquid Fluoride Reactors: A New Beginning for an Old Ideaguestcee6b0
Google Tech Talk by Dr. David LeBlanc about Liquid Fluoride Reactors. These are a class of nuclear reactor invented in the 1950s, abandoned in the 1970s, and becoming more interesting today.
The document summarizes a catastrophic accident that occurred at the Sayano-Shushenskaya hydroelectric power plant in Russia in 2009. A sudden surge of water pressure likely caused by a piece of debris getting stuck in a turbine resulted in the ejection of the turbine and flooding of the powerhouse. This led to 69 deaths, extensive damage totaling over $310 million, and power outages affecting aluminum production. Efforts were underway to drain water, remove debris, and make temporary repairs to prevent further damage over the winter.
The document discusses the CANDU nuclear reactor, a pressurized heavy water reactor designed in Canada. It provides details on the design of CANDU reactors, including their use of natural uranium fuel and heavy water as both moderator and coolant. CANDU reactors allow for online refueling without shutdown and have safety features like shutdown rods and poison injection. The document also outlines the pros and cons of CANDU reactors and their contribution to nuclear energy globally, with over 20 reactors operating or under construction in 7 countries.
This document discusses recent trends and the future of ultra deepwater oil field developments. It summarizes that developments in ultra deepwater have very high costs, prompting companies to consider more standardized and innovative solutions. Subsea wells and FPSOs have become the standard for field development below depths of around 2500-3000 meters. New technologies like subsea separation, direct electrical heating of flowlines, and subsea power distribution are being successfully implemented and will likely become more common. Future field developments are expected to utilize more standardized components coupled with innovative technologies to reduce costs and maximize recovery in ultra deepwater environments over the next 5-10 years.
International Journal of Engineering Research and DevelopmentIJERD Editor
This document discusses failure mechanisms in turbine blades of gas turbine engines. It begins by providing background on gas turbine engines and noting that turbine blade failures account for 42% of failures in some studies. The main failure mechanisms discussed are fatigue, creep, and corrosion. Fatigue can be low-cycle or high-cycle depending on the number of stress cycles and can initiate from cracks. Creep is stress-related deformation that increases with temperature and time. It can cause blade tips to rub casing. Corrosion can occur when blade coatings are removed from tip contact exposing the alloy.
This document discusses failure mechanisms in turbine blades of gas turbine engines. It begins by providing background on gas turbine engines and noting that turbine blade failures account for 42% of failures in some studies. The main failure mechanisms discussed are fatigue (low cycle and high cycle), creep, and thermo-mechanical fatigue. Low cycle fatigue is driven by starting and stopping and results from thermal stresses from rapid temperature changes. High cycle fatigue is caused by smaller vibrational stresses over many cycles. Creep results from long-term exposure to high stresses and temperatures and causes blades to deform over time. Thermo-mechanical fatigue is caused by thermal gradients across blades that induce cyclic stresses during operation. Case studies are provided to illustrate how these failure mechanisms impact
NRC Meeting 512 - Power Uprate via Plutoniumsyottovasikka
NRC 512th Meeting - Public discussion archive revealed with illustrations.
Read how Catastrophic failures due to uprating (adding Plutonium) cause only mild discussion. All 'Catastrophic' upratings rubber stamped by G.E. mules... Shaky control processes, including banal G.E. fraud - revealed. Causes no action...
Readability enhanced Public Domain documrent derived from NRC archives.
Nuclear Regulatory Commission http://www.nrc.gov/
Fueling AI with Great Data with Airbyte WebinarZilliz
This talk will focus on how to collect data from a variety of sources, leveraging this data for RAG and other GenAI use cases, and finally charting your course to productionalization.
The document summarizes the Fukushima Daiichi nuclear power plant accident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, risks to spent fuel pools, and sources of information on the incident. The earthquake caused a station blackout when the tsunami disabled backup diesel generators, leading to a loss of cooling and partial meltdowns in three reactor cores over several days before cooling was restored. Hydrogen explosions damaged some buildings housing the reactors.
The document summarizes the Fukushima Daiichi nuclear power plant accident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, risks to spent fuel pools, and sources of information on the incident. The earthquake caused a station blackout when the tsunami disabled backup diesel generators, leading to a loss of cooling and partial meltdowns in three reactor cores over several days before cooling was restored. Hydrogen explosions damaged some buildings housing the reactors.
The document summarizes the Fukushima Daiichi nuclear power plant incident in March 2011. It describes the plant design, the progression of the accident following the earthquake and tsunami, radiological releases on and off site, and risks to the spent fuel pools. The earthquake caused a station blackout which led to a loss of cooling and partial meltdowns in reactors 1, 2, and 3 over subsequent days. Hydrogen explosions damaged some buildings but the reinforced concrete containment structures remained intact. Offsite releases were limited but led to short term evacuations within 20 km.
Fukushima Daiichi Nuclear Power Station Accident April19 2011Joe Miller
This document provides an overview of the Fukushima Daiichi nuclear accident that occurred in 2011 following an earthquake and tsunami in Japan. It discusses the plant designs, accident progression, spent fuel pools, radiological releases, and impact on US reactors. Key events included the loss of off-site power and emergency diesel generators due to flooding, melting of reactor cores due to lack of cooling, hydrogen explosions, and venting of radioactive gases. Lessons learned included enhancing backup cooling capabilities and emergency procedures for extreme events.
The document provides basic design information about BWR3 and BWR4 reactors, which are the types used at the Fukushima Daiichi nuclear power plant. It describes the Mark I containment system, typical reactor vessel configurations, and the reactor core isolation cooling system. It then summarizes the events at Fukushima Daiichi following the 2011 earthquake and tsunami, including loss of cooling, hydrogen explosions, fuel damage in reactors 1-3, and challenges with spent fuel pools.
The document discusses both internal and external factors that will influence the future development of nuclear power. Internally, factors like nuclear accidents, reactor designs, waste disposal, and public perceptions of radiation hazards will be important. Externally, energy demand, limitations on fossil fuels, concerns about climate change, and the feasibility of renewable energy will also impact prospects. However, there are still large uncertainties, and expanding nuclear power faces potential difficulties related to the pace of construction, uranium resources, waste issues, proliferation risks, and ensuring safety.
1. The document summarizes a project to inspect GE90 engines on Boeing 777 aircraft operated by Emirates due to issues with the stage 1 high pressure turbine shrouds. The author planned and oversaw inspections and engine removals to implement a permanent modification.
2. As maintenance planning officer, the author's role was to minimize operational impacts through precise planning of the monthly inspection schedule and engine removals in coordination with other departments. Technical knowledge of the engines and inspection process was required.
3. Through careful analysis of inspection findings and coordination between teams, the author was able to identify deterioration trends and schedule engine removals to implement modifications before any incidents occurred, closing the inspection requirement.
IRJET- Analysis of Cooling Fluid Interaction and Force Generated in a Pis...IRJET Journal
This document discusses analysis of cooling fluid interaction and force generated in a piston cylinder assembly. It begins with an abstract that outlines the goal of analyzing cooling fluid effects and cavitation in internal combustion engines using simulation. It then provides background on cavitation phenomena and stages. It describes the operation of internal combustion diesel engines, including the four strokes and cooling system. Equations are presented for forces on piston cylinder components under various assumptions. The document aims to simulate cavitation effects on cylinder liners and identify methods to increase engine component life.
The Hallam Nuclear Power Facility in Lancaster County, Nebraska was a former nuclear reactor that operated from 1962 to 1964. It was decommissioned and dismantled in the late 1960s, with some low-level radioactive materials entombed onsite. Current activities involve annual groundwater monitoring to ensure the stability of the entombed reactor. The site is 7.3 hectares and estimated costs for long-term stewardship activities from 1998 to past 2070 are $46,000 annually on average. The primary long-term activity is groundwater monitoring to ensure no contamination has migrated from the buried materials.
The document provides an overview of AEP's Mountaineer Commercial Scale Carbon Capture & Storage (CCS II) Project Phase I and lessons learned. Key points include: (1) The project aimed to demonstrate Alstom's Chilled Ammonia Process CO2 capture technology and deep saline CO2 storage at commercial scale. (2) Technical challenges included integrating the capture system with the existing power plant and variable coal supply, and managing water from the capture process. (3) Lessons involved selection of anhydrous ammonia as the reagent, exhaust stack options, water management approaches, steam sourcing for the capture system, and using variable speed pumping for CO2 compression and injection.
This document discusses the Fukushima Daiichi nuclear disaster in March 2011 in Japan. It provides details on:
1. How the earthquake and subsequent tsunami damaged the plant's cooling systems, leading to reactor meltdowns. The tsunami overwhelmed sea walls and flooded backup diesel generators.
2. How the loss of cooling led to a rise in pressure that opened steam relief valves, lowering water levels in reactor vessels. This exposed nuclear fuel and caused melting. Hydrogen explosions also occurred.
3. How radioactive materials were released into the environment after containment venting and other failures, spreading contamination. The accident progression highlights vulnerabilities from natural disasters and issues with the plant's design and emergency response.
ESS-Bilbao Initiative Workshop. Overview of cryo-modules for proton acceleratorsESS BILBAO
The document provides an overview of cryomodule design for proton accelerators. Cryomodule design is optimized based on factors like the accelerated particle properties, beam energy requirements, and operating mode (pulsed or CW). Two main cryomodule concepts are discussed - the TESLA cryostring concept, which integrates many cavities and magnets into long cryomodule units to maximize efficiency, and the SNS concept of independent, replaceable cryomodule units. The TESLA design rationale aims for high filling factor, moderate costs, effective alignment, and reproducible assembly. Consequences include integrating the cryomodule and cryogenic distribution to minimize thermal losses and employing long cryomodule strings supplied by a central cryogenic
Liquid Fluoride Reactors: A New Beginning for an Old Ideaguestcee6b0
Google Tech Talk by Dr. David LeBlanc about Liquid Fluoride Reactors. These are a class of nuclear reactor invented in the 1950s, abandoned in the 1970s, and becoming more interesting today.
The document summarizes a catastrophic accident that occurred at the Sayano-Shushenskaya hydroelectric power plant in Russia in 2009. A sudden surge of water pressure likely caused by a piece of debris getting stuck in a turbine resulted in the ejection of the turbine and flooding of the powerhouse. This led to 69 deaths, extensive damage totaling over $310 million, and power outages affecting aluminum production. Efforts were underway to drain water, remove debris, and make temporary repairs to prevent further damage over the winter.
The document discusses the CANDU nuclear reactor, a pressurized heavy water reactor designed in Canada. It provides details on the design of CANDU reactors, including their use of natural uranium fuel and heavy water as both moderator and coolant. CANDU reactors allow for online refueling without shutdown and have safety features like shutdown rods and poison injection. The document also outlines the pros and cons of CANDU reactors and their contribution to nuclear energy globally, with over 20 reactors operating or under construction in 7 countries.
This document discusses recent trends and the future of ultra deepwater oil field developments. It summarizes that developments in ultra deepwater have very high costs, prompting companies to consider more standardized and innovative solutions. Subsea wells and FPSOs have become the standard for field development below depths of around 2500-3000 meters. New technologies like subsea separation, direct electrical heating of flowlines, and subsea power distribution are being successfully implemented and will likely become more common. Future field developments are expected to utilize more standardized components coupled with innovative technologies to reduce costs and maximize recovery in ultra deepwater environments over the next 5-10 years.
International Journal of Engineering Research and DevelopmentIJERD Editor
This document discusses failure mechanisms in turbine blades of gas turbine engines. It begins by providing background on gas turbine engines and noting that turbine blade failures account for 42% of failures in some studies. The main failure mechanisms discussed are fatigue, creep, and corrosion. Fatigue can be low-cycle or high-cycle depending on the number of stress cycles and can initiate from cracks. Creep is stress-related deformation that increases with temperature and time. It can cause blade tips to rub casing. Corrosion can occur when blade coatings are removed from tip contact exposing the alloy.
This document discusses failure mechanisms in turbine blades of gas turbine engines. It begins by providing background on gas turbine engines and noting that turbine blade failures account for 42% of failures in some studies. The main failure mechanisms discussed are fatigue (low cycle and high cycle), creep, and thermo-mechanical fatigue. Low cycle fatigue is driven by starting and stopping and results from thermal stresses from rapid temperature changes. High cycle fatigue is caused by smaller vibrational stresses over many cycles. Creep results from long-term exposure to high stresses and temperatures and causes blades to deform over time. Thermo-mechanical fatigue is caused by thermal gradients across blades that induce cyclic stresses during operation. Case studies are provided to illustrate how these failure mechanisms impact
NRC Meeting 512 - Power Uprate via Plutoniumsyottovasikka
NRC 512th Meeting - Public discussion archive revealed with illustrations.
Read how Catastrophic failures due to uprating (adding Plutonium) cause only mild discussion. All 'Catastrophic' upratings rubber stamped by G.E. mules... Shaky control processes, including banal G.E. fraud - revealed. Causes no action...
Readability enhanced Public Domain documrent derived from NRC archives.
Nuclear Regulatory Commission http://www.nrc.gov/
Fueling AI with Great Data with Airbyte WebinarZilliz
This talk will focus on how to collect data from a variety of sources, leveraging this data for RAG and other GenAI use cases, and finally charting your course to productionalization.
Driving Business Innovation: Latest Generative AI Advancements & Success StorySafe Software
Are you ready to revolutionize how you handle data? Join us for a webinar where we’ll bring you up to speed with the latest advancements in Generative AI technology and discover how leveraging FME with tools from giants like Google Gemini, Amazon, and Microsoft OpenAI can supercharge your workflow efficiency.
During the hour, we’ll take you through:
Guest Speaker Segment with Hannah Barrington: Dive into the world of dynamic real estate marketing with Hannah, the Marketing Manager at Workspace Group. Hear firsthand how their team generates engaging descriptions for thousands of office units by integrating diverse data sources—from PDF floorplans to web pages—using FME transformers, like OpenAIVisionConnector and AnthropicVisionConnector. This use case will show you how GenAI can streamline content creation for marketing across the board.
Ollama Use Case: Learn how Scenario Specialist Dmitri Bagh has utilized Ollama within FME to input data, create custom models, and enhance security protocols. This segment will include demos to illustrate the full capabilities of FME in AI-driven processes.
Custom AI Models: Discover how to leverage FME to build personalized AI models using your data. Whether it’s populating a model with local data for added security or integrating public AI tools, find out how FME facilitates a versatile and secure approach to AI.
We’ll wrap up with a live Q&A session where you can engage with our experts on your specific use cases, and learn more about optimizing your data workflows with AI.
This webinar is ideal for professionals seeking to harness the power of AI within their data management systems while ensuring high levels of customization and security. Whether you're a novice or an expert, gain actionable insights and strategies to elevate your data processes. Join us to see how FME and AI can revolutionize how you work with data!
Skybuffer SAM4U tool for SAP license adoptionTatiana Kojar
Manage and optimize your license adoption and consumption with SAM4U, an SAP free customer software asset management tool.
SAM4U, an SAP complimentary software asset management tool for customers, delivers a detailed and well-structured overview of license inventory and usage with a user-friendly interface. We offer a hosted, cost-effective, and performance-optimized SAM4U setup in the Skybuffer Cloud environment. You retain ownership of the system and data, while we manage the ABAP 7.58 infrastructure, ensuring fixed Total Cost of Ownership (TCO) and exceptional services through the SAP Fiori interface.
Trusted Execution Environment for Decentralized Process MiningLucaBarbaro3
Presentation of the paper "Trusted Execution Environment for Decentralized Process Mining" given during the CAiSE 2024 Conference in Cyprus on June 7, 2024.
leewayhertz.com-AI in predictive maintenance Use cases technologies benefits ...alexjohnson7307
Predictive maintenance is a proactive approach that anticipates equipment failures before they happen. At the forefront of this innovative strategy is Artificial Intelligence (AI), which brings unprecedented precision and efficiency. AI in predictive maintenance is transforming industries by reducing downtime, minimizing costs, and enhancing productivity.
Digital Marketing Trends in 2024 | Guide for Staying AheadWask
https://www.wask.co/ebooks/digital-marketing-trends-in-2024
Feeling lost in the digital marketing whirlwind of 2024? Technology is changing, consumer habits are evolving, and staying ahead of the curve feels like a never-ending pursuit. This e-book is your compass. Dive into actionable insights to handle the complexities of modern marketing. From hyper-personalization to the power of user-generated content, learn how to build long-term relationships with your audience and unlock the secrets to success in the ever-shifting digital landscape.
Salesforce Integration for Bonterra Impact Management (fka Social Solutions A...Jeffrey Haguewood
Sidekick Solutions uses Bonterra Impact Management (fka Social Solutions Apricot) and automation solutions to integrate data for business workflows.
We believe integration and automation are essential to user experience and the promise of efficient work through technology. Automation is the critical ingredient to realizing that full vision. We develop integration products and services for Bonterra Case Management software to support the deployment of automations for a variety of use cases.
This video focuses on integration of Salesforce with Bonterra Impact Management.
Interested in deploying an integration with Salesforce for Bonterra Impact Management? Contact us at sales@sidekicksolutionsllc.com to discuss next steps.
Dandelion Hashtable: beyond billion requests per second on a commodity serverAntonios Katsarakis
This slide deck presents DLHT, a concurrent in-memory hashtable. Despite efforts to optimize hashtables, that go as far as sacrificing core functionality, state-of-the-art designs still incur multiple memory accesses per request and block request processing in three cases. First, most hashtables block while waiting for data to be retrieved from memory. Second, open-addressing designs, which represent the current state-of-the-art, either cannot free index slots on deletes or must block all requests to do so. Third, index resizes block every request until all objects are copied to the new index. Defying folklore wisdom, DLHT forgoes open-addressing and adopts a fully-featured and memory-aware closed-addressing design based on bounded cache-line-chaining. This design offers lock-free index operations and deletes that free slots instantly, (2) completes most requests with a single memory access, (3) utilizes software prefetching to hide memory latencies, and (4) employs a novel non-blocking and parallel resizing. In a commodity server and a memory-resident workload, DLHT surpasses 1.6B requests per second and provides 3.5x (12x) the throughput of the state-of-the-art closed-addressing (open-addressing) resizable hashtable on Gets (Deletes).
Freshworks Rethinks NoSQL for Rapid Scaling & Cost-EfficiencyScyllaDB
Freshworks creates AI-boosted business software that helps employees work more efficiently and effectively. Managing data across multiple RDBMS and NoSQL databases was already a challenge at their current scale. To prepare for 10X growth, they knew it was time to rethink their database strategy. Learn how they architected a solution that would simplify scaling while keeping costs under control.
This presentation provides valuable insights into effective cost-saving techniques on AWS. Learn how to optimize your AWS resources by rightsizing, increasing elasticity, picking the right storage class, and choosing the best pricing model. Additionally, discover essential governance mechanisms to ensure continuous cost efficiency. Whether you are new to AWS or an experienced user, this presentation provides clear and practical tips to help you reduce your cloud costs and get the most out of your budget.
HCL Notes and Domino License Cost Reduction in the World of DLAUpanagenda
Webinar Recording: https://www.panagenda.com/webinars/hcl-notes-and-domino-license-cost-reduction-in-the-world-of-dlau/
The introduction of DLAU and the CCB & CCX licensing model caused quite a stir in the HCL community. As a Notes and Domino customer, you may have faced challenges with unexpected user counts and license costs. You probably have questions on how this new licensing approach works and how to benefit from it. Most importantly, you likely have budget constraints and want to save money where possible. Don’t worry, we can help with all of this!
We’ll show you how to fix common misconfigurations that cause higher-than-expected user counts, and how to identify accounts which you can deactivate to save money. There are also frequent patterns that can cause unnecessary cost, like using a person document instead of a mail-in for shared mailboxes. We’ll provide examples and solutions for those as well. And naturally we’ll explain the new licensing model.
Join HCL Ambassador Marc Thomas in this webinar with a special guest appearance from Franz Walder. It will give you the tools and know-how to stay on top of what is going on with Domino licensing. You will be able lower your cost through an optimized configuration and keep it low going forward.
These topics will be covered
- Reducing license cost by finding and fixing misconfigurations and superfluous accounts
- How do CCB and CCX licenses really work?
- Understanding the DLAU tool and how to best utilize it
- Tips for common problem areas, like team mailboxes, functional/test users, etc
- Practical examples and best practices to implement right away
Monitoring and Managing Anomaly Detection on OpenShift.pdfTosin Akinosho
Monitoring and Managing Anomaly Detection on OpenShift
Overview
Dive into the world of anomaly detection on edge devices with our comprehensive hands-on tutorial. This SlideShare presentation will guide you through the entire process, from data collection and model training to edge deployment and real-time monitoring. Perfect for those looking to implement robust anomaly detection systems on resource-constrained IoT/edge devices.
Key Topics Covered
1. Introduction to Anomaly Detection
- Understand the fundamentals of anomaly detection and its importance in identifying unusual behavior or failures in systems.
2. Understanding Edge (IoT)
- Learn about edge computing and IoT, and how they enable real-time data processing and decision-making at the source.
3. What is ArgoCD?
- Discover ArgoCD, a declarative, GitOps continuous delivery tool for Kubernetes, and its role in deploying applications on edge devices.
4. Deployment Using ArgoCD for Edge Devices
- Step-by-step guide on deploying anomaly detection models on edge devices using ArgoCD.
5. Introduction to Apache Kafka and S3
- Explore Apache Kafka for real-time data streaming and Amazon S3 for scalable storage solutions.
6. Viewing Kafka Messages in the Data Lake
- Learn how to view and analyze Kafka messages stored in a data lake for better insights.
7. What is Prometheus?
- Get to know Prometheus, an open-source monitoring and alerting toolkit, and its application in monitoring edge devices.
8. Monitoring Application Metrics with Prometheus
- Detailed instructions on setting up Prometheus to monitor the performance and health of your anomaly detection system.
9. What is Camel K?
- Introduction to Camel K, a lightweight integration framework built on Apache Camel, designed for Kubernetes.
10. Configuring Camel K Integrations for Data Pipelines
- Learn how to configure Camel K for seamless data pipeline integrations in your anomaly detection workflow.
11. What is a Jupyter Notebook?
- Overview of Jupyter Notebooks, an open-source web application for creating and sharing documents with live code, equations, visualizations, and narrative text.
12. Jupyter Notebooks with Code Examples
- Hands-on examples and code snippets in Jupyter Notebooks to help you implement and test anomaly detection models.
Main news related to the CCS TSI 2023 (2023/1695)Jakub Marek
An English 🇬🇧 translation of a presentation to the speech I gave about the main changes brought by CCS TSI 2023 at the biggest Czech conference on Communications and signalling systems on Railways, which was held in Clarion Hotel Olomouc from 7th to 9th November 2023 (konferenceszt.cz). Attended by around 500 participants and 200 on-line followers.
The original Czech 🇨🇿 version of the presentation can be found here: https://www.slideshare.net/slideshow/hlavni-novinky-souvisejici-s-ccs-tsi-2023-2023-1695/269688092 .
The videorecording (in Czech) from the presentation is available here: https://youtu.be/WzjJWm4IyPk?si=SImb06tuXGb30BEH .
TrustArc Webinar - 2024 Global Privacy SurveyTrustArc
How does your privacy program stack up against your peers? What challenges are privacy teams tackling and prioritizing in 2024?
In the fifth annual Global Privacy Benchmarks Survey, we asked over 1,800 global privacy professionals and business executives to share their perspectives on the current state of privacy inside and outside of their organizations. This year’s report focused on emerging areas of importance for privacy and compliance professionals, including considerations and implications of Artificial Intelligence (AI) technologies, building brand trust, and different approaches for achieving higher privacy competence scores.
See how organizational priorities and strategic approaches to data security and privacy are evolving around the globe.
This webinar will review:
- The top 10 privacy insights from the fifth annual Global Privacy Benchmarks Survey
- The top challenges for privacy leaders, practitioners, and organizations in 2024
- Key themes to consider in developing and maintaining your privacy program
Taking AI to the Next Level in Manufacturing.pdfssuserfac0301
Read Taking AI to the Next Level in Manufacturing to gain insights on AI adoption in the manufacturing industry, such as:
1. How quickly AI is being implemented in manufacturing.
2. Which barriers stand in the way of AI adoption.
3. How data quality and governance form the backbone of AI.
4. Organizational processes and structures that may inhibit effective AI adoption.
6. Ideas and approaches to help build your organization's AI strategy.
Best 20 SEO Techniques To Improve Website Visibility In SERPPixlogix Infotech
Boost your website's visibility with proven SEO techniques! Our latest blog dives into essential strategies to enhance your online presence, increase traffic, and rank higher on search engines. From keyword optimization to quality content creation, learn how to make your site stand out in the crowded digital landscape. Discover actionable tips and expert insights to elevate your SEO game.
Generating privacy-protected synthetic data using Secludy and MilvusZilliz
During this demo, the founders of Secludy will demonstrate how their system utilizes Milvus to store and manipulate embeddings for generating privacy-protected synthetic data. Their approach not only maintains the confidentiality of the original data but also enhances the utility and scalability of LLMs under privacy constraints. Attendees, including machine learning engineers, data scientists, and data managers, will witness first-hand how Secludy's integration with Milvus empowers organizations to harness the power of LLMs securely and efficiently.
Generating privacy-protected synthetic data using Secludy and Milvus
Plan B
1. “ Plan-B” An Alternative Liquidation* Strategy of Fukushima Daiichi NPP May 21, 2011 Satoshi Sato [email_address] International Access Corporation *: A term “liquidation” is used in this document to generally mean various activities directly and indirectly associated with restoration of safe state of each affected reactor in Fukushima Daiichi NPP. This follows a precedent in which workers involved in the emergency actions on the Chernobyl site during the accident and the subsequent clean-up operations were called “Liquidators”.
2. Abbreviations Standby Gas Treatment System SGTS Emergency Procedure Guidelines EPG BWR Owners Group BWROG Fission Product FP Overhead Crane OHC Fuel Handling Machine FHM Core-Concrete Interaction CCI Reactor Pressure Vessel RPV Spent Fuel Pool SFP Independent Spent Fuel Storage Installation ISFSI Greater Than Class C (Cask for High Level Radiation Waste) GTCC Spent Nuclear Fuel SNF Nuclear Power Plant NPP
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8. Summary - Reactor Original Function as Secondary Containment totally lost due to H2 explosion on Refueling Floor. Remaining part of building still reasonably good. Overhead Crane (OHC) and Fuel Handling Machine (FHM) not available. Barrier integrity no longer maintained. Details not confirmed. Barrier integrity no longer maintained. Bottom Head Penetrations severely damaged. Totally destroyed 1 Function as Secondary Containment still reasonably maintained even after H2 explosion. OHC and FHM still fully functioning. Barrier integrity severely degraded due to H2 explosion inside or outside Torus. Ditto Ditto 2 Ditto Not affected Not affected Empty 4 Same as Unit 1, except that some portions lower than Refueling Floor also degraded due to H2 explosion Same as Unit 1 Ditto Ditto 3 Reactor Building Primary Containment Reactor Pressure Vessel Reactor Core Unit Severely damaged Severely damaged Function Severely damaged Possibly still partly maintained but not confirmed Barrier Integrity
9. Unit 4 Unit 3 Unit 2 Unit 1 State of Reactor Building, Unit 1 to 4 looking from east as of March 20
10. Unit 3 Unit 4 State of Reactor Building, Unit 3 and 4 looking from west as of March 20
13. Melt-Down through Core Plate Predicted to occur 2 hours following complete loss of cooling capability. Several previous experiments suggested steam explosion not likely. Core Shroud Core Plate Reactor Core Molten Core Water No Doubt
14. Further Melt-Down through Core Plate Actual Complete Loss of Cooling Capability (Official Announcement by Government on May 16, 2011) No Doubt 06h43m 3 06h29m 2 14h09m 1 Duration Unit
15. Degradation of Reactor Pressure Vessel Bottom Head Creep rupture begins to occur at ~240-deg C below melting point (1500-deg C) of vessel material (low alloy steel), allowing some leakage of highly contaminated water containing fractured pieces of fuel pellets. Highly Likely
17. Further Degradation of Reactor Pressure Vessel Bottom Head Drywell Sump Pit Pedestal Pedestal Doorway Possible
18. Major Degradation of Reactor Pressure Vessel Bottom Head and Core-Concrete Interaction (CCI), Resulting in Significant Amount of Release of Radioactive Aerosol Pedestal Doorway Pedestal H 2 O, CO 2 H 2 O, CO 2 H 2 , CO Aerosol Aerosol Aerosol Aerosol Not very likely, but could have happened depending on cooling evolution during early stage.
19. Beginning of Primary Containment Failure Pedestal Doorway Pedestal Aerosol Aerosol Aerosol Aerosol H 2 , CO H 2 O, CO 2 H 2 O, CO 2 Not very likely, but could have happened depending on cooling evolution during early stage.
25. Residual Heat Generation 2 months after shutdown 0 2,381 2,381 1,380 Thermal Output (MWt) 0 2.4 2.4 1.4 Estimated Residual Heat (MWt) 0.1% of rated Thermal Output 0 784 784 460 Electrical Output (MWe) 0 548 548 400 # of Fuel Assembly in Rx. 4 3 2 1 Unit
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27. Unit 4 SFP Top view of fuel rack by remote underwater TV camera. Difficult to draw any conclusion about fuel integrity only based on this information. Fuel inspection by “sipping” is warranted.
28. Residual Heat Generation 11/30/’10 6/19/’10 9/16/’10 3/25/’10 Hottest Spent Fuel Discharged (Date of beginning of last refueling outage) Spent Fuel Pool New Fuel Storage Vault 1331 514 587 292 1.8 0.23 0.46 0.07 Estimated Residual Heat Generation Rate (MWt) 204 52 28 100 Number of Fuel Assembly 4 3 2 1 Unit
58. ISFSI Pad and Spent Fuel Storage Casks Vertical Horizontal
59.
60. Back to “Green Field” as of 9/5/2007 Actual and Future Yankee Rowe Decommissioning Schedule
61. Cased in container on 11/20/1996 Departed from site on 4/27/1997 Loaded on to railcar for 1800km transportation Arrival at Barnwell Site for subsurface repository on 5/7/1997 Reactor Vessel Disposal 3.6m-dia. x 8.1m-tall, weighing 165tons 80 tons of concrete poured inside and outside vessel
62. Large volume of subsurface soil found contaminated with tritium (H-3). Numbers indicate H-3 concentration in groundwater in pCi/L. EPA drinkable level is 20,000pCi/L.
71. Note that the dose limit for Emergency Workers is 250mSv. 8,400 18,200 46,500 mSv/h 3 2 1 Unit Possible for all buildings other than Rx. Bldg. of Unit 1 to 3 after some decontamination efforts. Not practical for Rx. Bldg. of Unit 1 to 3 due to high contamination level. Implosion Already done for Unit 4 Rx. Not practical for other units due to too much activity load. Chemical Decontamination Possible for Unit 4. Not practical for other units due to harsh radiological environment for workers. (Drywell Dose Rate as of May 20, 2011.) Separate RPV from All Other Connecting Systems Already done for Unit 4. Not practical for other units due to high contamination level. Remove Rx. Internals by High Pressure Abrasive Water Jet Application for Fukushima NPP Units Technique
78. Source: OECD/NEA “Chernobyl Ten Years on Radiological and Health Impact – An Assessment by the NEA Committee on Radiation Protection and Public Health” November 1995 Cs-137 Contamination 10 years later Vicinity of Fukushima NPP 80km Equivalent dose rate of 555kBq/m 2 contamination is 1.8 μ Sv/h or 15.8mSv/y. Blue colored region on land represents dose rate greater than 0.3 μ Sv/h as of 3/19/2011. 500km
84. Residual Heat Generation 2 months after shutdown 1 hour after shutdown 0 2,381 2,381 1,380 Thermal Output (MWt) 0 24 24 14 Estimated Residual Heat (MWt) 1% of rated Thermal Output 0 784 784 460 Electrical Output (MWe) 0 548 548 400 # of Fuel Assembly in Rx. 4 3 2 1 Unit
85. Major Degradation of Reactor Pressure Vessel Bottom Head and Core-Concrete Interaction (CCI), Resulting in Significant Amount of Release of Radioactive Aerosol Pedestal Doorway Pedestal H 2 O, CO 2 H 2 O, CO 2 H 2 , CO Aerosol Aerosol Aerosol Aerosol
86. Pedestal Doorway Pedestal Aerosol Aerosol Aerosol Aerosol H 2 , CO H 2 O, CO 2 H 2 O, CO 2 Beginning of Primary Containment Melt-Through
87. Gross Failure of Primary Containment due to Melt-Down Progression Aerosol Aerosol Aerosol Aerosol
102. Specific Strategies Strategy-A SFP Not Affected Strategy-II 2 Strategy-B Strategy-I Reactor Systems Not Affected 4 Strategy-B Strategy-II 3 Strategy-B Strategy-II 1 Spent Fuel Pool Reactor Unit
111. Helium is a standard cooling medium for high temperature gas reactors. GT-MHR (Gas Turbine – Module Helium Reactor)
112. A* B* To be added Scrubber/Gas Cooler Ventilation System Mode-1/2 Heat Sink Gravel Flow from Suppression Chamber to Drywell *: See “proposed line-up” for system interfaces for A and B for each unit. Option A
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114. Copper Sphere Shell Zeolite Mixing several different constituents may be considered
151. To Ventilation Fan and Gas Treatment System Wet Scrubber Water level Operation Mode 1, and Mode 2
152. Operation Mode Favorable Thermal Characteristic of Helium Not Required Required Required Cleanup System 3 2 1 Mode Natural Convection Non-contaminated Air Low (<100kW) Forced Cooling Contaminated Air Medium (100-350kW) Forced Cooling Contaminated Helium High (>350kW) Power Cooling Medium Heat Load J/kg ・ K Air = 1 W/m ・ K 1012 1 0.0316 Air 5192 5.53 0.1663 He Heat Capacity Relative Thermal Conductivity Thermal Conductivity Medium
159. Ultimate Configuration with Operation Mode 3 All contaminated equipment and materials are permanently buried in-situ. Paradigm Shift !! This concept, in spite of huge cost benefit expected, significantly deviates from the conventional approach.
162. Water Treatment (1) Highly Contaminated Water Currently Stored in Various Pools at Site Vitrification Canisters On-site Repository Concentrated Radioactive Liquid Treatment System Cement Aggregate Contaminated Concrete Rubble (Optional) Processed Water (slight contamination allowed) Ready-Mixed Concrete < 5,000Bq/cm 3 < 0.065mSv/h 20 v/v% 80 v/v% For Entombment Work
163. Dose Rate Calculation of Homogenously Contaminated Concrete Assumption: 500TBq in 10 5 m 3 , or 5,000Bq/cm 3 of processed water Water Content in Ready Mixed Concrete = 20% Calculation: Low enough!
164. Heat Generation Calculation of Homogenously Contaminated Concrete Assumption: 500TBq in 10 5 m 3 of water, or 5,000Bq/cm 3 Water Content in Ready Mixed Concrete = 20% Energy Release per Disintegration = 1MeV Calculation: Total energy release rate = (1.6 x 10 -13 J) x (5 x 10 14 /sec) = 80W Temperature increase based on black body radiation q” = σ T 4 σ = 5.67 x 10 -8 q” = 80/(4 π r 2 ) r = 28.8m q” = 7.7 x 10 -3 W/m 2 T = 19-deg C Low enough!
165. Water Treatment (2) Desalination System Cement Aggregate Contaminated Concrete Rubble (Optional) Processed Water (still slightly contaminated) Ready-Mixed Concrete < 5,000Bq/cm 3 < 0.065mSv/h 20 v/v% 80 v/v% Contaminated Water within Intake Area For Encasing Concrete Rubble
168. Intake Area Intake Facility (typ.) Backwash Valve Pit (typ.) Control Bldg. (typ.) Turbine Bldg. (typ.) Rx. Bldg. (typ.) RW Bldg. (typ.) Before Unit 2 Unit 1 Unit 3 Unit 4
169. Entombed Reactors After Protection Fence against Aircraft Impact Stack Concrete rubble generated from demolition of all other structures is encased in the large concrete block(s). Tsunami Barrier Tsunami Barrier Wave Breakers for Tsunami Protection Original Shoreline
170. ISFSI for SNF and any potential GTCC Waste On-Site Repository for Vitrified Canisters Legend: Monitoring Post Ground Water Sampling Point Protected Area Main Gate New Site Boundary Monitoring Facility Conceptual New Site Arrangement
177. District for New Industry/Community Development Entombed Reactors (Units 1 to 4) Survived Reactors (Units 5 and 6) Solar Thermal Power Beyond “Liquidation” Previous Site Boundary
178. Target Overall Schedule FS, Bidding, Design/Engineering Mode 1 Mode 2 Mode 3 Mode 1 Mode 2 Mode 3 Sipping Transportation Campaign Unit 2, SFP Unit 1 to 3, Reactor Construct On-Site Repository Facility Unit 1, 3, and 4, SFP Unit 4, Reactor 4y 6y Public Acceptance (Workshop) 10y 8y 2y Activities EI 2 -D Projects Demolition of other structures Water Treatment, Vitrification Build Liquidators’ Villages Recruit Liquidators Expand On-Site Liquidation Infrastructures New Industry/Community Development Construct ISFSI (for Unit 2 SNF) Construct Intake Area Tsunami Barriers Licensing Review on EI 2 -D (Safety Analysis)