scholarly journals The study of capability natural uranium as fuel cycle input for long life gas cooled fast reactors with helium as coolant

2016 ◽  
Author(s):  
Menik Ariani ◽  
Octavianus Cakra Satya ◽  
Fiber Monado ◽  
Zaki Su’ud ◽  
Hiroshi Sekimoto
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Long Life

scholarly journals Optimized core design for small long-life gas cooled fast reactors with natural uranium-thorium-blend as fuel cycle input

2020 ◽  
Vol 1568 ◽  
pp. 012015
Author(s):  
M Ariani ◽  
Supardi ◽  
A Johan ◽  
F Monado ◽  
Z Su’ud ◽  
...  
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Long Life

Optimization of Small Long Life Gas Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input

2012 ◽  
Vol 260-261 ◽  
pp. 307-311 ◽  
Author(s):  
Menik Ariani ◽  
Z. Su'ud ◽  
Fiber Monado ◽  
A. Waris ◽  
Khairurrijal ◽  
...  
Keyword(s):  
Nuclear Power ◽  
Power Plants ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Natural Circulation ◽  
Average Power ◽  
Natural Uranium ◽  
Energy Utilization ◽  
Fast Reactors ◽  
Long Life

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.

Conceptual Design Study of Small 400 MWt Pb-Bi Cooled Modified Candle Burn-Up Based Long Life Fast Reactors

2014 ◽  
Vol 983 ◽  
pp. 353-356 ◽  
Author(s):  
Zaki Suud ◽  
H. Sekimoto
Keyword(s):  
Conceptual Design ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Natural Uranium ◽  
Multiplication Factor ◽  
Fast Reactors ◽  
Design Study ◽  
Accumulation Pattern ◽  
Pattern Change ◽  
Long Life

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.

Design Study of Small Lead-Cooled Fast Reactors Using SiC Cladding and Structure

2006 ◽  
Author(s):  
Abu Khalid Rivai ◽  
Minoru Takahashi
Keyword(s):  
Power Distribution ◽  
Inner Core ◽  
Fuel Cycle ◽  
Outer Core ◽  
Structure Type ◽  
Natural Uranium ◽  
Neutron Energy Spectrum ◽  
Fast Reactors ◽  
Steel Type ◽  
Type Reactor

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.

scholarly journals Conceptual design study on very small long-life gas cooled fast reactor using metallic natural Uranium-Zr as fuel cycle input

2014 ◽  
Author(s):  
Fiber Monado ◽  
Menik Ariani ◽  
Zaki Su'ud ◽  
Abdul Waris ◽  
Khairul Basar ◽  
...  
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Design Study ◽  
Long Life

Design study of gas cooled fast reactors using natural uranium as fuel cycle input employing radial shuffling strategy

2012 ◽  
Author(s):  
Feriska Handayani Irka ◽  
Zaki Su'ud ◽  
Menik Aryani ◽  
Ferhat Aziz ◽  
H. Sekimoto
Keyword(s):  
Fuel Cycle ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Design Study

The feasibility study of small long-life gas cooled fast reactor with mixed natural Uranium/Thorium as fuel cycle input

2012 ◽  
Author(s):  
Menik Ariani ◽  
Zaki Su’ud ◽  
Abdul Waris ◽  
Khairurrijal ◽  
Fiber Monado ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Long Life

A Once-Through Fuel Cycle for Fast Reactors

2010 ◽  
Vol 132 (10) ◽  
Author(s):  
Kevan D. Weaver ◽  
John Gilleland ◽  
Charles Ahlfeld ◽  
Charles Whitmer ◽  
George Zimmerman
Keyword(s):  
Energy Policy ◽  
Traveling Wave ◽  
Policy Development ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Washington Dc ◽  
Fast Reactors ◽  
Design Work ◽  
National Energy Policy ◽  
Water Reactors

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.

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