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Energy and Environment
Published in T.M. Aggarwal, Environmental Control in Thermal Power Plants, 2021
Current fission reactors in operation around the world are second or third generation systems, with most of the first-generation systems having been retired some time ago. Research into advanced generation IV reactor types was officially started by the Generation IV International Forum (GIF) based on eight technology goals, including to improve nuclear safety, improve proliferation resistance, minimize waste, improve natural resource utilization, the ability to consume existing nuclear waste in the production of electricity, and decrease the cost to build and run such plants. Most of these reactors differ significantly from current operating light water reactors, and are generally not expected to be available for commercial construction before 2030.
Nuclear Power Technologies through Year 2035
Published in D. Yogi Goswami, Frank Kreith, Energy Conversion, 2017
Kenneth D. Kok, Edwin A. Harvego
To address these concerns and to fully realize the potential contributions of nuclear power to future energy needs in the United States and worldwide, the development of a new generation of reactors, termed Generation IV, was initiated in 2001. The intent or objective of this effort is to develop multiple Generation IV nuclear power systems that would be available for international deployment before 2030. The development of the Generation IV reactor systems is an international effort, initiated by the U.S. Department of Energy (DOE) with participation from 10 countries. These countries established a formal organization referred to as the Generation IV International Forum (GIF). The GIF countries included Argentina, Brazil, Canada, France, Japan, the Republic of Korea, the Republic of South Africa, Switzerland, the United Kingdom, and the United States. The intent of the GIF is “… to develop future-generation nuclear energy systems that can be licensed, constructed, and operated in a manner that will provide competitively priced and reliable energy products while satisfactorily addressing nuclear safety, waste, proliferation, and public perception concerns.”
The future of nuclear energy
Published in Tina Soliman Hunter, Ignacio Herrera Anchustegui, Penelope Crossley, Gloria M. Alvarez, Routledge Handbook of Energy Law, 2020
Nuclear reactors can be classified differently according to certain features of their designs (e.g., coolant type or moderator technology). However, given the development of nuclear technology over time, a distinction based on generations is often used to classify nuclear reactors, providing a useful chronological roadmap. That said, at present most of the world’s nuclear reactors belong to the Generation II category.52 As technology is being developed further,53 however, Generation III, III+ and even Generation IV fission designs are set to replace older nuclear reactors as the latter approach the final stages of their life cycle and new reactor plants are commissioned. The transition from Generation II reactors to more modern designs is already underway. The first Generation III reactor was built in Japan in 1996 (ADBWR),54 while the first Generation III+ design became operational in Russia in 2016 (VVER-1200/392M) at the Novovoronezh power plant.55 Generation IV and Generation V reactors are still in the design phase and have not yet been built although Generation IV reactors are expected to make it to commercial construction between 2020 and 2030.56 Research in next generation reactors is not limited to isolated efforts of specific nations but is also supported by a number of international organizations and international ventures. Several international initiatives are pursuing joint development of Generation III and Generation IV nuclear reactors. These include the Generation IV International Forum (GIF) initiated by the US Department of Energy in 2000 to share scientific knowledge and to pursue development of six selected Generation IV reactor technologies.57 The Multinational Design Evaluation Programme (MDEP),58 a joint effort of the US Nuclear Regulatory Commission (NRC) and the French Nuclear Safety Authority (ASN), is pursuing creation of a harmonized set of regulatory requirements and practices for both Generation III and future Generation IV reactors. Additionally, the European Sustainable Industrial Initiative (ESNII),59 launched by the European Commission in 2010, will actively support Generation IV reactor technologies.
Numerical Modeling and Simulation of Melting Phenomena for Freeze Valve Analysis in Molten Salt Reactors
Published in Nuclear Science and Engineering, 2023
Davide Tartaglia, Antonio Cammi, Carolina Introini, Stefano Lorenzi
Generation-IV reactors[1] are nuclear reactor concepts having the potential to bring various benefits to the nuclear industry, including increased safety, reduced proliferation risks, economical affordability, sustainability of the fuel cycle, and management of the waste inventory. Among them, the molten salt fast reactor (MSFR) is the current reference design studied within the Generation-IV International Forum, and its safety barriers are the object of the SAMOSAFER European project.aSee https://samosafer.eu/. A mixture of chloride or fluoride salt containing the dissolved nuclear fuel is pumped and circulated through the primary system, acting as coolant and fuel.[2] In case of an accident, the molten salt is drained by gravity from the core to a casing located below the core, where proper cooling and subcriticality are ensured. The draining system is connected through 16 pipes to the bottom of each one of the external loops.
Preconceptual Design of Multifunctional Gas-Cooled Cartridge Loop for the Versatile Test Reactor—Part I
Published in Nuclear Science and Engineering, 2022
Piyush Sabharwall, Kevan Weaver, N. K. Anand, Chris Ellis, Xiaodong Sun, Di Chen, Hangbok Choi, Rich Christensen, Brian M. Fronk, Joshua Gess, Yassin Hassan, Igor Jovanovic, Annalisa Manera, Victor Petrov, Rodolfo Vaghetto, Silvino Balderrama-Prieto, Adam J. Burak, Milos Burger, Alberto Cardenas-Melgar, Londrea Garrett, Genevieve L. Gaudin, Daniel Orea, Reynaldo Chavez, Byunghee Choi, Noah Sutton, Ken William Ssennyimba, Josh Young
The lack of fast neutron spectrum test capabilities in the United States and the approaching end of operational lifetimes in some international fast neutron spectrum test facilities create a need for irradiation testing facilities to provide irradiation research capabilities. The number of currently operating facilities is limited and will eventually shrink as some currently active reactors reach the end of their operational lifetimes. The VTR is being developed to fill this gap and provide a much needed center for irradiation testing and advanced reactor research. It will be used for the development of Generation IV reactors, which include sodium-cooled fast reactors, gas-cooled fast reactors (GFRs), molten salt reactors, and lead-cooled or lead/bismuth-cooled fast reactors. The inherent features of most advanced reactors help reduce design complexity, enhance operational safety, and enable more efficient use of nuclear fuel.