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The Nuclear Power Institute of China has developed many small and medium (SMR) reactors including those used for nuclear seawater desalination, nuclear district heating, and nuclear-powered commercial ships, multi-purpose small modular pressurized reactors. Developing nuclear energy is a measure of meeting national economic development and satisfying the need for energy conservation and reduction of emissions. Large size nuclear power units are less suitable to regional networks and non-electric fields, highlighting the importance of studying small and medium reactors. Small reactors are also in high demand for developing countries and the vast Midwest of China. Domestic cities and regions are also in urgent need of nuclear energy for heating, desalination, and district heating.

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New speakers confirmed:
• Dr. Kathryn Huff, Assistant Secretary for Nuclear Energy;
• David Wright, Commissioner, Nuclear Regulatory Commission;
• Todd Shrader, Deputy Director for Project Management, Office of Clean Energy Demonstrations;
• James Schaefer, Senior Managing Director, Guggenheim Securities;
• Richard Arnold, Spokesperson, Consolidated Group of Tribes and Organizations;
• Sharon Fain, Vice President, Rocky Mountain Power Wyoming;
• Rita Meyer, Executive Outreach, TerraPower;
• Christine Csizmadia, Senior Manager for State Outreach, Nuclear Energy Institute
• Rick McLeod, President/CEO, Savannah River Site Community Reuse Organization;
• Dave McCormack, Executive Director, Clean Energy Supplier Alliance;
• Karl Dye, President/CEO, Tri-City Development Council; and
• Jackie Toth, Deputy Director, Good Energy Collective; addition to representatives from the U.S. Department of Energy’s Office of Nuclear Energy and Office of Clean Energy Demonstrations, national laboratories, University of Michigan’s Fastest Path to Zero, the Nuclear Energy Institute, the Gateway for Accelerated Innovation in Nuclear, the National Reactor Innovation Center, and more!
To better understand how to match potential host community strengths and needs with those of advanced nuclear project developers, ECA’s Energy Communities Forum on Hosting New Nuclear Development will:
• Provide a venue for nuclear technology and project developers to meet and interact with interested potential host communities, with exhibition booth spaces and separate, small meeting room availability.
• Share lessons learned from communities and developers hosting nuclear power facilities or federal nuclear missions and outline what local government needs to understand and should consider as potential hosts for nuclear projects.
• Facilitate discussions to better understand the outlook for new nuclear development and provide realistic timelines for local governments and economic development entities looking at siting, regulation, public-private partnerships and how to build support from the ground-up. 
The agenda features five case studies on new nuclear development in Idaho; Richland, Washington; Kemmerer, Wyoming; Oak Ridge, Tennessee; and Portsmouth, Ohio with presentations by the teams – from the developer, utility, local government, and local economic development entities – on progress being made and the challenges that remain.
For questions - including discounts for ECA members and local governments - please contact Sarah Templeton, ECA Program Manager, at

* Discuss a potential new DOE Program on innovative materials research for fuel cladding for advanced reactors.
* Review the results of the GAIN Innovative Materials Research Workshop help on June 15, 2022.
* Inform program objectives and gather supplier, developer, university researcher, and national laboratory input to determine priority research directions.

The scope of the Innovative Cladding Materials Research Program will include the following:

* Innovative cladding materials research, including core materials that provide structure (e.g., grid plates, materials that are removed from the core along with refueling activities)
* Innovative characterization and testing methods
* Innovative new methods of qualifying material "quicker"
* Research needs spanning the next 20 years

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Molten salt reactors (MSRs) are being considered as one of the potential nuclear options to meet future energy demands. While the MSR designs differ from the more traditional light water reactor, many of the waste streams are similar between the concepts. Other streams differ drastically. This presentation outlines strategies for the treatment and processing of MSR-type wastes from concepts of reconditioning and recycle of certain components to partitioning and direct immobilization of other waste components. The primary focus will be on the management of fuel salt related wastes while other streams unique to MSRs are also briefly discussed.

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Austenitic stainless steels are widely used as in-core materials in current nuclear systems, due to a combination of corrosion resistance, ductility, and other mechanical properties. However, in the next generation nuclear systems that will be operated at higher temperature and higher level of neutron irradiation, the use of austenitic stainless steels is largely avoided mostly due to poor void swelling resistance. In this regard, our research group developed an austenitic SS with uniformly distributed nanosized NbC precipitates, named as ARES-6P, by controlling chemical composition and thermo-mechanical processing. To demonstrate the radiation resistance, heavy ion irradiation was performed at high temperatures to the damage level of ~200 displacement per atom (dpa). The measured void swelling of ARES-6P was 2‒3%, which was considerably less compared to commercial 316 stainless steel and comparable to ferritic martensitic steels. In addition, the increment of hardness measured by nano-indentation was much smaller for ARES-6P compared to 316 stainless steel. Though some nanosized NbC precipitates were dissociated under relatively high dose rate (~5.0 × 10-4 dpa s-1), a sufficient number of NbC precipitates remained to act as sink sites for the point defects, resulting in superior radiation resistance. Both significantly less void swelling and less irradiation hardening indicate the superior irradiation resistance of ARES-6P for the application of next generation nuclear systems. Register NOW at:
Please join us for this GIF-IAEA-NEA joint webinar addressing the Role of Nuclear Energy in Reducing CO2 Emissions. The event features 20-minute presentations from each of our guest speakers, followed by a 30- minute panel discussion in responses to audience questions.

Distiguished Guest Speakers: Dr. Shannon Bragg-Sitton, Mr. Wei Huang, Ms. Diane Cameron
Moderators: Dr. Patricia Paviet and Dr. Tatjana Jevremovic

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Purpose: Convene supply chain and procurement leaders from the energy industry sector to explore gaps, opportunities, and solutions in the advanced nuclear supply chain. Discussions will bring awareness and teamwork to ensure sustainable and competitive deployment of advanced reactors. 

Key Topics:
• Perspectives in Supply Chain Gaps and Challenges
• Solutions and Opportunities: When to Team- When to Compete
• Next Steps: Formalizing Action

For MORE information click on the following link:
Join us for a national workshop exploring strategies for and the many benefits of repurposing legacy fossil fuel infrastructure, including closed coal mines, coal power plants, and orphaned oil and gas wells.

Leveraging and transforming legacy fossil fuel infrastructure creates the opportunity for a skilled workforce to access new sources of high-quality jobs and for states and communities to increase tax revenues. As clean energy, manufacturing, and other innovative companies grow, energy communities are an attractive option for locating new and expanding operations because they often offer:

A skilled workforce with knowledge of industrial operations
Entrenched community relationships
Access to rail lines, ports, highways, and other distribution infrastructure
Electrical interconnect equipment and direct grid connections
Industrial land, facilities, and potentially even site and permitting licenses
Register for this half-day workshop featuring expertise on site remediation and reclamation, worker training and upskilling of dislocated workers, and the broad range of options for capitalizing on existing fossil fuel infrastructure.
In the industry and especially in the nuclear field, simulation software plays an important part on the study of new prototypes, as building scale 1 prototype is both complex and expensive. To assess new design options and validate associated simulation software, most experiments are performed on small-scale mock-ups. However, distortions of a studied phenomenon can occur from a small-scale model to a prototype: this is known as scale effects. Without understanding of these effects, results from models cannot be transposed to the prototype scale and numerical results cannot be validate either.
In the French SFR project, an important problematic is the raise of the core jets in the upper plenum for specific operating conditions. When these jets raise, the flow pattern in the vessel is modified and leads to thermal fluctuations reducing the lifetime of the reactor’s components because of thermal fatigue. While this raise can be observed on small-scale mock-up, it is important to be able to characterize both this phenomenon and its transposition. For this purpose, Benjamin Jourdy works on a methodology based on bibliography synthesis and experimental results, leading to the conception of a new mock-up dedicated to this study. Register Here:
The Clean Energy Ministerial’s Nuclear Innovation: Clean Energy Future (NICE Future) initiative and the International Youth Nuclear Congress (IYNC) are proud to present a webinar focused on how nuclear technologies support global communities at the local level.

This event will demonstrate opportunities for communities to be uplifted by nuclear technologies and breakthrough innovations. Learn how countries and organizations are working to bring the social, economic, and environmental benefits of nuclear energy to communities around the world as they make clean energy transitions.

Imagine a future of energy that is more integrated and customized to local needs. Let's explore the work on the front lines of the energy transitions – states! Our speakers will share observations about emerging trends, defining the real work of energy and environmental justices, and the emerging analysis tools available. Our speakers will share how thinking far into the future is shaping their work today.

Join us as we examine the opportunities, challenges, and innovations needed for Shaping our Carbon-Free Future.​

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The ESFR-SMART project is what in the Anglo-Saxon world is called a “working horse" or a “concept car”. Its role is to introduce, outside any constructive planning, new ideas for the future, which can be valuable guides for R&D. Unlike in an “industrial” project, which initially had a construction schedule, one can introduce innovative ideas, even if their lower technological-readiness level would require development and time. For these new ideas, research and first calculations were also performed during the project, to check their general feasibility and the absence of major impossibilities.

The presentation will show the design proposition for this SFR reactor including the
experience feedback from European experience on Phénix, Superphénix, EFR and ASTRID. This design includes all improvements in response to the last safety rules issued after the Fukushima incident. Finally, the first calculations performed for the design validation are also explained with the necessary R&D.

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AccessBrookhaven is virtual event series that will share the different capabilities that Brookhaven National Laboratory offers to support industry’s research and development efforts and the funding opportunities offered by the U.S. U.S. Department of Energy (DOE) to support new innovation.

The second of the series will focus on advancing nuclear energy technology and how Brookhaven Lab’s capabilities can be accessed through the Gateway for Accelerated Innovation in Nuclear's (GAIN) Nuclear Energy Voucher Program.

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Has the COVID and Omicron variant kept you cooped up inside your home office?  Come to the GAIN Power Hour, a virtual networking event that doesn't require a COVID test.  For one hour, GAIN will 'seed the room' with U.S. Department of Energy (DOE) national laboratory staff so you can come, connect, and ask your questions.

Meimei Li, Advanced Materials and Manufacturing Technologies at Argonne National Laboratory

Bo Feng, Fast Reactor Program at Argonne National Laboratory

Patricia Paviet, Molten Salt Reactor Program at Pacific Northwest National Laboratory ​

There's no script, so bring your questions!

The purpose of this periodic advanced reactor stakeholder meetings is to share information and discuss topics releated to the development and licensing of advance reactors with the nuclear industry and other stakeholders.

The meeting notice can be found at the following link:
The purposed of this meeting is to discuss with the nuclear industry issues related to the NEI 21-07, Revision 0, "Technology Inclusive Guidance for Non-Light Water Reactors Safety Analysis Report Content for applicants Utilizing NEI 18-04 Methodology." Revision )-B of this document is available in ADAMS at Accession No. ML 21343A292. 

The meeting notice can be found at the following link:
In recent years, micro-reactor concepts have attracted increasing attention in the nuclear industry due to the market demand for flexible, reliable, and sustainable power and heat on-site for industrial or federal installations or remote communities. Micro-reactor AGile Non-nuclear Experimental Test-bed (MAGNET) is at Idaho National Laboratory (INL) with an initial focus on the thermal and structural performance of heat pipe cooled micro-reactors. System Analysis Module (SAM) code is a multi-dimensional modern software tool provided by Argonne National Laboratory (ANL). This webinar will review the designs of heat-pipe micro reactors, steady-state and transient simulation of MAGNET by SAM, to explore the performance limit by heat transfer and temperature distribution.

Don’t miss NEI's International Uranium Fuel Seminar at the Westin Savannah Nov. 7-9. It is a prime networking opportunity for nuclear fuel and utility leaders.
Explore the issues impacting the nuclear fuel cycle by attending two half-day sessions on fuel policy, markets, and trade issues, as well as plenty of networking opportunities.

Conference Webpage:
Pu​rpose​: To engage the nuclear industry in discussions on advanced manufacturing codes, standards, demonstrations, and advanced techniques to accelerate commercialization.
  * Understand applications of machine learning and digital twin tools, through collaboration with codes and standards entities
  * Define “uncertainty," including measurements for uncertainty and how it can be minimized
  * Identify cross-cutting demonstration or benchmarking products or projects that are suitable for early adoption by industry

Topics to be Presented:
 - Overviews of US Department of Energy (DOE) and US Nuclear Regulatory Commission (NRC) MSR released activities
 - Overviews of the DOE Office of Nuclear Energy (NE) MSR technology development and advanced modeling and simulation activities
 - DOE-NE and NRC sponsored MSR activities overviews
 - Salt chemistry
 - Salt irradiation
 - Modeling and simulation
 - Reactor operations and monitoring
 - Safety and licensing
 - Overviews of the current status from several MSR reactor developers Deployment

For more information and registration link please follow this URL:
A new key research initiative at EPRI is focusing on technology for Nondestructive Evaluation (NDE) and online monitoring for high
temperature applications. As an important part of this effort, we are looking to build a network of vendors and technology
researchers to facilitate collaborations in this area.

We are also hosting a technical workshop as part of this initiative. The objective of the workshop is to identify promising sensor
technologies and solutions. The workshop will help increase awareness and facilitate collaboration between EPRI and others.
Standards and regulations in many countries discuss graded approach; some
even require it. Criteria or justifications for grading are commonly addressed.
Not much, however, is discussed about the methods that can be used to grade
a process once the criteria are met.
This webinar will remove any mystery associated with graded approach. Mr.
Chermak asserts there are only two ways to grade one’s approach to Quality
Assurance — and they are very simple.
Join us for an interactive discussion of this topic! We look forward to your
company while we learn about and delve into graded approach.

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The Nuclear Innovation Bootcamp is back - virtually! Today we are opening FREE registration to our annual event taking place on August 5th from 12:00 - 15:15 EDT. There are also limited-capacity side events taking place earlier and later in the day. This will be the Bootcamp’s first entirely public event since its founding in 2016 so register now and share the event with your colleagues!

This year's program will feature panel discussions on 21st century applications for advanced reactors, the technology’s implications for environmental justice, and its role within the broader cleantech ecosystem. Consistent with past years, the panelists will represent a broad range of backgrounds from within and outside the nuclear space.
We look forward to seeing you in August!

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The post-war dawn of ‘The Atomic Age’ promised abundant energy and prosperity. However, questions around safety and economic viability contributed to nuclear fission going out of vogue by the late 1980s, culminating in the weekly lampooning of nuclear power on The Simpsons.
Today, the new urgency to decarbonize has put nuclear fission back on the table. What has changed on the technical front that might make it safer? Can it be economically viable compared to solar and wind power? Will people want a nuclear fission reactor in their town? Will fission power be necessary for us to reach our climate objectives?
We are in the middle of a shift in expert opinion on the viability of nuclear fission power. Join our panel of experts Wednesday, August 4 at 3 pm ET/12 pm PT to understand the current thinking around nuclear fission in relation to decarbonization.

For more information:
The 12th annual Modeling, Experimentation, and Validation (MeV) Summer School will be organized by Argonne National Laboratory and held virtually from July 19-30, 2021.
This year’s theme is “Holistic Innovation: Integrating Methods, Experiments, and People to Advance Nuclear Technology.”
The announcement can be viewed and downloaded by clicking the flyer image below. We respectfully ask that you forward this information to students and colleagues that would benefit from the school or help distribute this information throughout your institution.
Information and online application instructions are available in the flyer and on the school’s website at
The deadline for applications is March 30, 2020.
2021 MeV Summer School Organizing Committee
Florent Heidet, ANL Dean
Tyler J. Gerczak, ORNL Dean
Curtis Smith, INL Dean
In Service Inspection is a major challenge to consider for future Generation IV Reactors safety. Therefore, a large focus of R&D work has been performed since 2010 in France for the Sodium Fast Reactor systems (SFR), mainly dedicated to the inspection of reactor block structures, primary components and circuits, and Power Conversion System main components (Heat Exchangers). In Service Inspection requirements have to be taken into account since the early preconceptual design phase, then consolidated through the basic design phase with more detailed specifications leading to increase the inspection tools ability for immersed sodium structures of SFRs, at about 200°C (shut down conditions). Inspection within the main vessel should be performed either with transducers immersed in sodium (with associated in sodium robotics) and with transducers located out of sodium medium. Nondestructive Examination, Telemetry and Imaging are qualified with experimental in-water and then in-sodium testing, using
ultrasonic transducers. Experimental results are then compared to simulations using French CIVA software platform results. Repair was also part of this program, with laser system development. This webinar provides a technical overview of this
ISI&R program that involves specific international collaborations done through GENIV mainly. Of course, it also benefits to other Gen4 systems.

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A webinar series to understand the road that was taken to arrive at the current regulatory framework.

For more information and to register please go to:

Application Deadline for Cycle 2021-1 of the Industry Funding Opportunity Announce (FOA) Extended to May 28, 2021

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Join the Versatile Test Reactor (VTR) Program and the Nuclear Energy Institute for an in-depth dialogue about the VTR’s essential role in expanding the US’ world class research capabilities and supporting the next generation of nuclear power to help achieve a clean energy future.

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The development of critical design criteria for new advanced reactor systems, components, and materials requires an understanding of both fabrication and the irradiation environment during normal operating and accident conditions. Next-generation researchers and designers are therefore challenged not only by demands for improved performance, they must also work to shorten the development and commercialization lifecycle for new nuclear reactors and systems to remain competitive. This provides unique and exciting opportunities for all contributors to this field of study. This presentation will offer a strategic overview of the impact that advanced manufacturing has on the lifecycle of new generation reactors. By evaluating state-of-the-art practices found in other large manufacturing industries, this presentation provides an overview of major innovation areas that are considered to benefit the GEN-IV systems (SFR, GFR, LFR, FSMR...). Synergetic advanced manufacturing approaches beneficial to the collective GEN-IV systems, with some examples of differentiating approaches necessary for specific reactor designs, are discussed. Furthermore, new paradigms in licensing approaches for additively manufactured parts will be discussed.

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