scholarly journals Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

2017 ◽  
Author(s):  
Jason M. Harp ◽  
Luca Capriotti ◽  
Steven L. Hayes ◽  
Pavel G. Medvedev ◽  
Douglas L. Porter
Keyword(s):  
Fast Reactor ◽  
Thermal Reactor

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.

scholarly journals Testing Fast Reactor Fuels in a Thermal Reactor: A Comparison Report

2017 ◽  
Author(s):  
Luca Capriotti ◽  
Jason Michael Harp ◽  
Steven Lowe Hayes ◽  
Pavel G. Medvedev ◽  
Douglas Lloyd Porter
Keyword(s):  
Fast Reactor ◽  
Thermal Reactor

Testing fast reactor fuels in a thermal reactor

2018 ◽  
Vol 328 ◽  
pp. 154-160 ◽  
Author(s):  
Pavel Medvedev ◽  
Steven Hayes ◽  
Samuel Bays ◽  
Stephen Novascone ◽  
Luca Capriotti
Keyword(s):  
Fast Reactor ◽  
Thermal Reactor

Environmental aspects of the fast reactor fuel cycle

1990 ◽  
Vol 331 (1619) ◽  
pp. 395-408 ◽  
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Thermal Reactor ◽  
Environmental Aspects ◽  
Fuel Cycles ◽  
Global Environmental ◽  
Delay Times ◽  
Fast Reactor Fuel ◽  
Reactor Accidents

The main characteristics that differentiate a developed fast reactor fuel cycle from the thermal reactor fuel cycles operating now are the higher fissile content of the fuel, the greater incentive to reprocess fuel at shorter delay times and the elimination of uranium mining. The local and global environmental impacts of a typical fuel cycle normalized to 1GW e a of output are estimated, including those from the fabrication, transport and reprocessing of fuel and from reactor operations. Radioactive emissions and radiation doses arising from these operations are compared with those from thermal reactor cycles. The risks of accidental discharges from reprocessing plants are discussed, but reactor accidents are not included. The requirements for safeguards are described. Typical inventories of radioactive wastes arising from reprocessing and from decommissioning have been calculated; the management and disposal of these wastes will pose no significant new problems. The overall result is that a transition from thermal to fast reactor fuel cycles should not result in any increase in environmental impact.

scholarly journals Analisis Kekritisan Sodium-Cooled Fast Reactor (SFR) Berdasarkan Variasi Bahan Bakar

2018 ◽  
Vol 7 (1) ◽  
pp. 69-72
Author(s):  
Revina Septi ◽  
Mohammad Ali Shafii ◽  
Feriska Handayani Irka ◽  
Zaki Su'ud
Keyword(s):  
Fast Reactor ◽  
Thermal Reactor ◽  
Code System ◽  
Region 10

Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi bahan bakar telah dilakukan. Variasi bahan bakar yang digunakan adalah MOX, UN-PuN, dan U-Zr. Reaktor ini menggunakan natrium sebagai pendingin dan parameter yang diamati adalah faktor multiplikasi (keff )pada teras reaktor. Penelitian ini dilakukan secara simulasi komputasi meggunakan kode SRAC (Standard Thermal Reactor Analysis Code System) dengan JENDL-32 sebagai library. Teras reaktor dibagi menjadi 10 region arah radial.  Pada awal operasi reaktor, masing-masing region diisi dengan bahan bakar uranium alam.  Setelah 10 tahun pembakaran, hasil burn up pada region 1 di shuffling ke region 2, hasil region 2 di shuffling ke region 3 dan seterusnya sampai hasil burn up di region 9 di shuffling ke region 10, hasil burn up region 10 dikeluarkan dari teras reaktor dan pada region 1 akan diisi dengan bahan bakar yang baru. Hasil penelitian menunjukkan bahwa bahan bakar MOX dan U-Zr memilki nilai keff  yang paling optimal digunakan pada reaktor SFR.Kata kunci: faktor multiplikasi keff , periode burn up, program SRAC, strategi shuffling

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