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Metal Fuel Development and Verification for Prototype Generation IV Sodium-Cooled Fast Reactor
- Source :
- Nuclear Engineering and Technology, Vol 48, Iss 5, Pp 1096-1108 (2016)
- Publication Year :
- 2016
- Publisher :
- Elsevier BV, 2016.
-
Abstract
- Metal fuel is being developed for the prototype generation-IV sodium-cooled fast reactor (PGSFR) to be built by 2028. U–Zr fuel is a driver for the initial core of the PGSFR, and U–transuranics (TRU)–Zr fuel will gradually replace U–Zr fuel through its qualification in the PGSFR. Based on the vast worldwide experiences of U–Zr fuel, work on U–Zr fuel is focused on fuel design, fabrication of fuel components, and fuel verification tests. U–TRU–Zr fuel uses TRU recovered through pyroelectrochemical processing of spent PWR (pressurized water reactor) fuels, which contains highly radioactive minor actinides and chemically active lanthanide or rare earth elements as carryover impurities. An advanced fuel slug casting system, which can prevent vaporization of volatile elements through a control of the atmospheric pressure of the casting chamber and also deal with chemically active lanthanide elements using protective coatings in the casting crucible, was developed. Fuel cladding of the ferritic–martensitic steel FC92, which has higher mechanical strength at a high temperature than conventional HT9 cladding, was developed and fabricated, and is being irradiated in the fast reactor.
- Subjects :
- Cladding (metalworking)
Materials science
020209 energy
Nuclear engineering
02 engineering and technology
Fuel element failure
law.invention
Sodium-cooled fast reactor
Sodium-cooled Fast Reactor
law
0202 electrical engineering, electronic engineering, information engineering
Irradiation Test
Waste management
Transuranic Fuel
Pressurized water reactor
Spent Fuel
Pyroelectrochemical
lcsh:TK9001-9401
Spent nuclear fuel
Thorium fuel cycle
Nuclear Energy and Engineering
Nuclear reactor core
Casting (metalworking)
Ferritic–Martensitic Steel
lcsh:Nuclear engineering. Atomic power
Metal Fuel
Subjects
Details
- ISSN :
- 17385733
- Volume :
- 48
- Database :
- OpenAIRE
- Journal :
- Nuclear Engineering and Technology
- Accession number :
- edsair.doi.dedup.....373facf5790d0e388933cced9d0ff65a