Announcements

Environmental Assessment commences for the MMR™ Plant at Chalk River – the first SMR in Canada
15 July 2019
USNC, Global First Power (GFP), and Ontario Power Generation (OPG) are pleased to announce that the Canadian Nuclear Safety Commission (CNSC) has issued the Notice of Commencement of an Environmental Assessment (EA) for our MMR™ Project at Chalk River, in Renfrew County, Ontario, Canada.

We will be working with the Canadian Nuclear Laboratories (CNL) to progress the EA for the plant, and look forward to engaging with our partners and stakeholders.

For more information see:
USNC, Global First Power (GFP), and Ontario Power Generation (OPG) submit first regulatory application for a Small Modular Reactor (SMR) in Canada.
2 April 2019
USNC, Global First Power (GFP), and Ontario Power Generation (OPG) achieve a significant milestone – submitting the first regulatory application for a Small Modular Reactor (SMR) in Canada. Submission of the application to the Canadian Nuclear Safety Commission (CNSC) builds on collaborative efforts of many organizations with the vision to bring the benefits of SMRs to Canada.

For more information see:
CNL advances project to third phase of process to site an MMR™ plant on a CNL site.
15 Feb 2019
CNL announced that Global First Power (GFP), with its key partners Ontario Power Generation (OPG) and Ultra Safe Nuclear Corporation (USNC), has progressed through the second stage of the site invitation process, and has been invited to participate in preliminary, non-exclusive discussions regarding land arrangements, project risk management, and contractual terms (Stage 3). These negotiations are not an indication of project approval, and the proposal and proponent must satisfy further stringent evaluation.

For more information see:
USNC’s MMR™ system completes first phase Vendor Design Review with the Canadian Nuclear Safety Commission.
7 Feb 2019
The Canadian Nuclear Safety Commission (CNSC) confirmed the successful completion of the Phase 1 Vendor Design Review by USNC for the MMR™ system.

The MMR™ reactor is a 15-thermal-megawatt micro modular reactor, with a net electrical output of approximately 5 megawatts. The MMR™ reactor concept draws on operational experience from the high-temperature gas-cooled reactors developed by the U.S., Germany, China, and Japan.

The MMR™ plant is aimed at providing low-cost, reliable, safe nuclear power to remote communities and mines in northern Canada.

“Completion of the initial phase of the VDR provides USNC with confidence that the concept and approach to the MMR™ plant will be acceptable to the CNSC. “ – Mark Mitchell – VP for Micro Reactors

USNC confirms their intent to continue with the second phase Vendor Design Review.

For more information see:
OPG partners with Global First Power to support USNC MMR™ reactor in Canada.
13 Nov 2018
Canada’s Ontario Power Generation (OPG) announced that they are partnering with Global First Power (GFP). GFP is USNC’s development partner focused on bringing USNC technology to remote mines and communities in Canada.



USNC welcomes OPG participation.

For more information see:
USNC appointed by UK BEIS to participate in the Advanced Modular Reactor (AMR) Feasibility and Development Project.
5 Sep 2018
USNC has been appointed by the UK Department for Business, Energy & Industrial Strategy (BEIS) to participate in the Advanced Modular Reactor (AMR) Feasibility and Development Project. Project Title: MMR™, a novel nuclear cogeneration system for multipurpose applications.

Ultra Safe Nuclear Corporation (USNC) has developed the Micro-Modular Reactor (MMR™), a 15 MWth High-Temperature, Gas-Cooled Reactor (HTGR) design, able to operate 20 years without refueling. The focus is on electricity supply to remote mines and communities in northern Canada. The MMR™ reactor uses innovative features that set it apart from other HTGR designs.

The MMR™ reactor uses USNC's proprietary Fully Ceramic Microencapsulated (FCM™) fuel. This fuel enhances the already very high fission product retention of TRISO particles. This allows for the design of reactors with extremely low release of fission products both during normal operation and accidents. FCM™ fuel coupled with the intrinsic characteristics of the MMR™ reactor design allow for an extremely simplified design of the plant while maintaining a robust safety case.

The MMR™ plant is designed to use an intermediate heat transfer loop, based on the molten salt technology successfully developed and deployed in Concentrating Solar Plants (CSP) over the last 10 years, to transfer the heat from the reactor to the Adjacent Plant. This allows the reactor to be decoupled from the client application. This makes the reactor very good for both generating electricity and process heat. An MMR™ plant can generate from 0–100% process heat, and 0–100% electrical power with the same flexibility as a gas boiler or gas turbine. The MMR™ plant is a small plant and is designed for mass production and modular construction. This contributes to its competitiveness. The MMR™ reactor is factory sealed, delivered, and retrieved after complete fuel depletion, resulting in a highly proliferation-resistant design. The MMR™ Design for Canada (MMR-REM™) is advanced and has undergone the Vendor Design Review (VDR) Phase 1 with the Canadian Nuclear Safety Commission (CNSC).

USNC consider that the MMR-REM™ plant may not be well suited to application in the UK. The feasibility study is aimed at identifying a specific UK application that is best suited to launching a UK-MMR™ reactor. The study will identify the technical, economic and regulatory barriers to deployment and put a plan in place to address them. We expect that this will be in the delivery of high temperature process heat that can be used to replace fossil fuels and to generate high-value products such as hydrogen.

For more information see:
USNC open sources our ASME BPVC Division 5 Subsection HHA Irradiated Graphite Analysis Code.
21 Aug 2017
The ASME Boiler and Pressure Vessel Code Published Division 5 in 2013. This included the provision for the design of graphite structures for advanced and high-temperature reactors.

USNC staff actively participated in the development of the AMSE code, and to support the use of the code, we have open sourced our ASME BPVC Division 5 Subsection HHA Irradiated Graphite Analysis Code.

For more information see: