Spent fuel characteristics for thorium‐uranium recycle in fluoride‐salt‐cooled solid‐fuel fast reactor

2021 ◽  
Author(s):  
Yu Peng ◽  
Guifeng Zhu ◽  
Yang Zou ◽  
Miaomiao Niu ◽  
Hongjie Xu
Keyword(s):  
Fast Reactor ◽  
Solid Fuel ◽  
Fluoride Salt ◽  
Spent Fuel ◽  
Fuel Characteristics

Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel

2017 ◽  
Vol 28 (11) ◽  
Author(s):  
Yu Peng ◽  
Gui-Feng Zhu ◽  
Yang Zou ◽  
Si-Jia Liu ◽  
Hong-Jie Xu
Keyword(s):  
Fast Reactor ◽  
Solid Fuel ◽  
Fluoride Salt

scholarly journals Study on CANDLE Burning Fast Reactor with Initial Core Using Plutonium from LWR Spent Fuel

2017 ◽  
Vol 131 ◽  
pp. 15-20 ◽  
Author(s):  
Hiroki Osato ◽  
Jun Nishiyama ◽  
Toru Obara
Keyword(s):  
Fast Reactor ◽  
Spent Fuel

scholarly journals Decay Heat of Fast Reactor Spent Fuel.

1999 ◽  
Vol 41 (9) ◽  
pp. 946-953 ◽  
Author(s):  
Takafumi AOYAMA ◽  
Tadahiko TORIMARU ◽  
Akihiro YOSHIDA ◽  
Yoshio ARII ◽  
Soju SUZUKI
Keyword(s):  
Fast Reactor ◽  
Spent Fuel ◽  
Decay Heat

The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant

2017 ◽  
Vol 101 ◽  
pp. 199-208 ◽  
Author(s):  
Yu Peng ◽  
Guifeng Zhu ◽  
Yang Zou ◽  
Yafen Liu ◽  
Xiaohan Yu ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Fluoride Salt ◽  
Reactor Coolant ◽  
Feasibility Research

scholarly journals Minor actinides transmutation in equilibrium cores of next generation FRs

2019 ◽  
Vol 5 (4) ◽  
pp. 353-359
Author(s):  
Alexander V. Egorov ◽  
Yurii S. Khomyakov ◽  
Valerii I. Rachkov ◽  
Elena A. Rodina ◽  
Igor R. Suslov
Keyword(s):  
Isotopic Composition ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Synergetic Effect ◽  
Transient State ◽  
Advanced Technology ◽  
Thermal Reactor ◽  
Spent Fuel ◽  
Operating Period ◽  
Nitride Fuel

The Russian Federation is developing a number of technologies within the «Proryv» project for closing the nuclear fuel cycle utilizing mixed (U-Pu-MA) nitride fuel. Key objectives of the project include improving fast reactor nuclear safety by minimizing reactivity changes during fuel operating period and improving radiological and environmental fuel cycle safety through Pu multi-recycling and МА transmutation. This advanced technology is expected to allow operating the reactor in an equilibrium cycle with a breeding ratio equaling approximately 1 with stable reactivity and fuel isotopic composition. Nevertheless, to reach this state the reactor must still operate in an initial transient state for a lengthy period (over 10 years) of time, which requires implementing special measures concerning reactivity control. The results obtained from calculations show the possibility of achieving a synergetic effect from combining two objectives. Using МА reprocessed from thermal reactor spent fuel in initial fuel loads in FR ensures a minimal reactivity margin during the entire fast reactor fuel operating period, comparable to the levels achieved in equilibrium state with any kind of relevant Pu isotopic composition. This should be combined with using reactivity compensators in the first fuel micro-campaigns. In the paper presented are the results of simulation of the overall life cycle of a 1200 MWe fast reactor, reaching equilibrium fuel composition, and respective changes in spent fuel nuclide and isotopic composition. It is shown that МА from thermal and fast reactors spent fuel can be completely utilized in the new generation FRs without using special actinide burners.

Cadmium Transport through Molten Salts in the Reprocessing of Spent Fuel for the Integral Fast Reactor

1993 ◽  
Vol 102 (3) ◽  
pp. 331-340 ◽  
Author(s):  
K. Michael Goff ◽  
Alfred Schneider ◽  
James E. Battles
Keyword(s):  
Fast Reactor ◽  
Molten Salts ◽  
Spent Fuel ◽  
Cadmium Transport
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