Dr. Satyen Baindur

Small & Modular Reactor (SMR) Related Links and Resources

Small and Modular Reactor Projects
Gas-Cooled Reactor Links
Liquid Metal-Cooled Reactor Links
Research Reactor Safety Assessment
Graded Approach to Regulatory Requirements
Non-Electric Applications of Nuclear Energy

Small and Modular Reactor (SMR) Projects and Links

US NRC Vision and Strategy Document for Non-Light Water Cooled Reactors - January 2017
US NRC Small Modular Reactor (SMR) and Advanced Reactor Technical and Policy Issues
IAEA Small and Medium-sized Reactor Page
IAEA SMR Status Document September 2012
IAEA 6th INPRO Forum - on SMR Licensing and Safety Issues      Final Report August 2013
IAEA ARIS Database - Advanced Reactor Information System
Idaho National Laboratory Small Modular Reactor Technology Center
Gateway for Accelerated Innovation in Nuclear (GAIN), at INL
UxC's SMR Research Center
Daniel T. Ingersoll: Deliberately Small Reactors and the Second Nuclear Era
IAEA TecDoc 1485: Status of Small Reactor Designs With Conventional Refueling (2005)
IAEA TecDoc 1536: Status of Small Reactor Designs Without Onsite Fueling (2007)
IAEA TecDoc 1451: Innovative Small and Medium Sized Reactors: Design Features, Safety Approaches and R&D Trends

Atomic Energy of Canada Ltd. (AECL) Nuclear Battery (via nuclearfaq.ca)
Deployable Electric Energy Reactor (DEER) Presentation by Jerry Cuttler Dunedin Energy
US Nuclear Regulatory Commission Advanced Non-Light Water & SMR Page
US NRC Policy Issues in Licensing Advanced Reactor Designs Page
Kristiina Soderholm PhD Thesis September 2013: Licensing Model Development for Small Modular Reactors

Light Water-cooled SMRs

International Reactor Innovative and Secure (IRIS)
mPower Reactor
KAERI System-integrated Modular Advanced Reactor (SMART)
The Kerena Boiling Water Reactor (Areva)
SMR,LLC's SMR-160 Reactor
The ATMEA1 Reactor (Areva-Mitsubishi joint venture)

Non-Light Water Cooled SMRs

Liquid Metal Cooled Reactors

Toshiba Super-Safe, Small and Simple (4S) Metallic fuel, movable-reflector controlled core
   The Galena, Alaska Project
Gen4Energy Gen4M (Gen4 Module) - Liquid Metal Cooled, Uranium-nitride fueled, fast-spectrum Reactor
GE-Hitachi Power Reactor Innovative Small Module (PRISM) - liquid-sodium cooled, U-Pu-Zr alloy fueled, fast spectrum Reactor
ARC Nuclear, LLC's ARC-100 concept - liquid sodium cooled, U-metal alloy fueled, fast spectrum reactor
Northern Nuclear's LEADIR-PS100 Lead-cooled Integral Passively-safe (TRISO-pebble U-fueled) reactor
Lead Cold Reactors' SEALER Swedish Advanced Lead-cooled (19.99% UOX fueled fast spectrum) reactor

Molten-Salt cooled Reactors

Terrestrial Energy Inc. Molten Salt Reactor
Transatomic Power Inc. Molten Salt Reactor
Moltex Energy: Stable Salt Reactor
Flibe Energy Inc. Liquid Fluoride Thorium Reactor (LFTR)
Kairos Power, LLC. Fluoride Salt-cooled High-Temperature Reactor (FHR)

Terra Power Inc. Traveling Wave Reactor (TWR)

Gas-cooled Reactors

Idaho National Laboratory (INL) Gas Cooled Reactor (GCR) Links

Pebble Bed Modular Reactor (PBMR) Website
Starcore Power (helium-cooled SMR)
U-Battery helium-cooled TRISO-fueled SMR
General Atomics Helium-Cooled Energy Multiplier Module (EM2)
The Remote Site-Modular Helium Reactor (RS-MHR)
Areva's New Technology Advanced Reactor System (ANTARES)

Gas-Cooled Reactor Safety Assessment

IAEA Gas-Cooled Reactors Links and Resources
Institut de Radioprotection et de Surete Nucleaire (IRSN): Department for the assessment of gas-cooled, fast neutron and experimental reactors (SEGRE)
IAEA Safety Report Series No. 54: Accident Analysis for Nuclear Power Plants with Modular High Temperature Gas-Cooled Reactors
IAEA TecDoc 1366: Safety Requirements for Innovative Reactors: Application to Modular High Temperature Gas-Cooled Reactors
IAEA TecDoc 1238Gas Turbine Power Conversion Systems for Modular HTGRs
IAEA TecDoc 1210Safety Related Design and Economic Aspects of HTGRs
IAEA TecDoc 1198Current Status and Future Development of Modular HTGR Technology
IAEA TecDoc 1163Heat Transport and Afterheat Removal for Gas Cooled Reactors Under Accident Conditions
IAEA TecDoc 1674Advances in High Temperature Gas Cooled Reactor Fuel Technology (May 2012)

US NRC NUREG/CR-6839: Fort St Vrain Operating Experience

Gen IV Description of Candidate Gas Cooled Reactor Systems
Gen4 International Forum - Gas-cooled Fast Reactor Description

Liquid Metal-Cooled Reactor Safety Assessment

Sodium as a Fast-Reactor Coolant - US DOE/NRC Presentation
IAEA TecDoc 1569: Liquid Metal-Cooled Reactors: Experience in Design and Operation
IPFM Publication September 2011 on Managing Spent Fuel from Nuclear Reactors
Joint ICTP-IAEA School on Physics and Technology of Fast Reactor Systems, 9-20 November 2009, Trieste.
IAEA-GIF Workshop on Safety Aspects of Sodium-Cooled Reactors, 23-25 June 2010, Vienna
Presentation on Safety Issues for Sodium-cooled Fast Reactors, FR'09, Kyoto, Japan, December 2009
2009 International Conference on Fast Reactors, Kyoto Japan (FR09), December 7-11, 2009.
IAEA: Fast Reactors - Conferences, Programs, Publications
IAEA TecDoc 1766 - Accelerator Driven Systems
IAEA TecDoc 1180: Unusual Occurrences during LMFR Operation.

Research Reactors

IAEA Integrated Safety Assessment for Research Reactors Page
IAEA Safety Reports Series No. 55: Safety Analysis for Research Reactors
IAEA Code of Conduct on the Safety of Research Reactors
IAEA TecDoc 1220 "Safety of Research Reactors" IAEA Safety Standards Series No. NS-R-4
IAEA Published Safety Standards for Research Reactors
IAEA Draft Standard DS396: Safety Assessment for Research Reactors and Preparation of the Safety Analysis Report
IAEA Draft Standard DS412: Ageing Management for Research Reactors
IAEA TecDoc 1625: Research Reactor Modernization and Refurbishment
IAEA TecDoc 1212: Strategic Planning for Research Reactors
IAEA Research Reactors Page

Graded Approach

IAEA Draft Standard DS351: The Use of a Graded Approach in the Application of the Safety Requirements for Research Reactors

Non-Electric Applications of Nuclear Energy

Proceedings IAEA International Conference on Non-Electric Applications of Nuclear Power, 2007, Japan
Canadian Nuclear Society Western Focus Seminar, Calgary, June 2009
Presentation on Applicability of 4S (Super-Safe, Small and Simple) [Sodium-cooled Fast] Reactor to Alberta Tar Sands at CNS Western Focus Seminar, Calgary 2009