A Once-Through Fuel Cycle for Fast Reactors

Author(s):  
Kevan D. Weaver ◽  
John Gilleland ◽  
Charles Ahlfeld ◽  
Charles Whitmer ◽  
George Zimmerman

A paradigm shift has altered the design targets for advanced nuclear energy systems that use a fast neutron spectrum. Whereas designers previously emphasized the ability of fast reactors to extend global reserves of fissile fuels, the overriding desire now is for reactor technologies that are “cleaner, more efficient, less waste-intensive, and more proliferation-resistant.” (Cheney, 2001, “U.S. National Energy Policy,” National Energy Policy Development Group, Washington, DC) This shift in priorities, along with recent design advances that enable high fuel burnup even when using fuels that have been minimally enriched, creates an opportunity to use fast reactors in an open nuclear fuel cycle. One promising route to this goal exploits a phenomenon known as a traveling wave, which can attain high burnups without reprocessing. A traveling-wave reactor (TWR) breeds and uses its own fuel in place as it operates. Recent design work has demonstrated that TWRs could be fueled almost entirely by depleted or natural uranium, thus reducing the need for initial enrichment. The calculations described here show that a gigawatt-scale electric TWR can achieve a burnup of 20%, which is four to five times that realized in current light water reactors. Burnups as high as 50% appear feasible. The factors that contribute to these high burnups and the implications for materials design are discussed.

Author(s):  
Kevan D. Weaver ◽  
John Gilleland ◽  
Charles Ahlfeld ◽  
Charles Whitmer ◽  
George Zimmerman

A paradigm shift has recently altered the design targets for advanced nuclear energy systems that use a fast neutron spectrum. A previous emphasis on extending fissile fuel reserves has been supplanted by a desire for reactor technologies that are “cleaner, more efficient, less waste-intensive, and more proliferation-resistant.” [1] This shift, along with recent advances in fast-reactor designs that enable high fuel burn-up even with fuels that have been minimally enriched, creates an opportunity to employ fast reactors in an open nuclear fuel cycle. These goals now appear feasible as a result of recent design work exploiting a phenomenon, known as a traveling wave, that can attain high burn-ups without reprocessing. A traveling-wave reactor (TWR) breeds and uses its own fuel in place as it operates. Fueled almost entirely by depleted or natural uranium, such reactors would also require little initial enrichment. We have performed calculations demonstrating that TWRs can achieve burn-ups of ≥20%, which is four to five times that realized in current LWRs. Burn-ups of up to 50% appear feasible. The factors that contribute to these high burn-ups and the implications for materials design will be discussed.


Author(s):  
Abu Khalid Rivai ◽  
Minoru Takahashi

Effects of SiC cladding and structure on neutronics of reactor core for small lead-cooled fast reactors have been investigated analytically. The fuel of this reactor was uranium nitride with 235U enrichment of 11% in inner core and 13% in outer core. The reactors were designed by optimizing the use of natural uranium blanket and nitride fuel to prolong the fuel cycle. The fuels can be used without reshuffling for 15 years. The coolant of this reactor was lead. A calculation was also conducted for steel cladding and structure type as comparison with SiC cladding and structure type. The results of calculation indicated that the neutron energy spectrum of the core using SiC was slightly softer than that using steel. The SiC type reactor was designed to have criticality at the beginning of cycle (BOC), although the steel type reactor could not have critical condition with the same size and geometry. In other words, the SiC type core can be designed smaller than the steel type core. The result of the design analysis showed that neutron flux distributions and power distribution was made flatter because the outer core enrichment was higher than inner core. The peak power densities could remain constant over the reactor operation. The consumption capability of uranium was quite high, i.e. 13% for 125 MWt reactor and 25% for 375 MWt reactor at EOC.


2020 ◽  
Vol 1568 ◽  
pp. 012015
Author(s):  
M Ariani ◽  
Supardi ◽  
A Johan ◽  
F Monado ◽  
Z Su’ud ◽  
...  

2012 ◽  
Vol 260-261 ◽  
pp. 307-311 ◽  
Author(s):  
Menik Ariani ◽  
Z. Su'ud ◽  
Fiber Monado ◽  
A. Waris ◽  
Khairurrijal ◽  
...  

In this study gas cooled reactor system are combined with modified CANDLE burn-up scheme to create small long life fast reactors with natural circulation as fuel cycle input. Such system can utilize natural Uranium resources efficiently without the necessity of enrichment plant or reprocessing plant. Therefore using this type of nuclear power plants optimum nuclear energy utilization including in developing countries can be easily conducted without the problem of nuclear proliferation. In this paper, optimization of Small and Medium Long-life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input has been performed. The optimization processes include adjustment of fuel region movement scheme, volume fraction adjustment, core dimension, etc. Due to the limitation of thermal hydraulic aspects, the average power density of the proposed design is selected about 75 W/cc. With such condition we investigated small and medium sized cores from 300 MWt to 600 MWt with all being operated for 10 years without refueling and fuel shuffling and just need natural Uranium as fuel cycle input. The average discharge burn-up is about in the range of 23-30% HM.


Author(s):  
Chellapandi Perumal ◽  
V. Balasubramaniyan ◽  
P. Puthiyavinayagam ◽  
Raghupathy Sundararajan ◽  
Madhusoodanan Kanakkil ◽  
...  

Indian nuclear power programme is being implemented in three stages taking in to consideration limited uranium resources and vast thorium resources in the country. The first stage consists of investing natural uranium in Pressurized Heavy Water Reactors (PHWR). This stage has the potential of 10 GWe. The second stage involves large scale deployment of Fast Breeder Reactors (FBR) with co-located fuel cycle facilities to utilize the plutonium and depleted uranium extracted from the PHWR spent fuel. This stage has a potential of about 300 GWe. In the third stage, effective utilization of the vast thorium resources is planned. Indira Gandhi Centre for Atomic Research (IGCAR) instituted in 1971 at Kalpakkam, is involved in the mission of developing the technology of FBR. A host of multidisciplinary laboratories are established in the centre around the central facility of the 40 MWt Fast Breeder Test Reactor (FBTR). Presently, the construction of indigenously designed MOX fueled 500 MWe Prototype Fast Breeder Reactor (PFBR) that started in 2003 is in advanced stage and commissioning activities are underway. The design of PFBR incorporates several state-of-art features and is foreseen as an industrial scale techno-economic viability demonstrator for the FBR program. Beyond PFBR, the proposal is to build one twin unit having two reactors, with each of improved design compared to PFBR, to be commissioned by 2025. Subsequently, towards rapid realization of nuclear power, the department is planning a series of metal fueled FBRs starting with a 500 MWe Metal fuel Demonstration Fast Breeder Reactor (MDFR-500) to be followed by industrial scale 1000 MWe metal fueled reactors. The paper discusses in detail the above aspects and highlights the activities carried out towards designing MDFR.


2012 ◽  
Author(s):  
Feriska Handayani Irka ◽  
Zaki Su'ud ◽  
Menik Aryani ◽  
Ferhat Aziz ◽  
H. Sekimoto

Author(s):  
I. A. Tereshchenko ◽  
S. O. Ustimenko

It is known that the IAEA considers options for a fuel cycle with light water reactors of new generation (LWR); however, the uranium reserves will not last forever, so the input of fast reactors in order to “close” the fuel cycle is currently the best option. Therefore, the preliminary calculations of the approximate cycle took place, and a comparative analysis of cycles using only LWR and the cycle with a gradual replacement of LWR by fast breeder reactors was carried out as well. It is appropriate, because there is a sufficiently large number of spent nuclear fuel now is accumulated in temporary storage, but soon it has to be either converted into fresh fuel or disposed (that is unacceptable in all respects). The main problem of the closed fuel cycle is usage of MOX-fuel, but this type of fuel is elaborated now and will be improved upon.


2014 ◽  
Vol 983 ◽  
pp. 353-356 ◽  
Author(s):  
Zaki Suud ◽  
H. Sekimoto

In this paper conceptual design study of modified CANDLE burn-up scheme based 400 MWt small long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input has been performed. In this study the reactor cores are subdivided into 10 parts with equal volume in the axial directions. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. For small reactor core, it is important to apply high breeding material, so that high volume fraction of 60% fuel volume fraction nitride fuel is applied. The effective multiplication factor initially at 1.005 but then continuously increases during 10 years of burn-up. The peak power density initially about 307 W/cc but then continuously decreases to 268 at the end of 10 years burn-up cycle. Infinite multiplication factor pattern change, conversion ratio pattern change, and Pu-239 accumulation pattern change shows strong acceleration of plutonium production in the first region which is located near the 10th region. Maximum discharged burn-up is 31.2% HM.


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