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

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

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.

Preliminary Design Study of Medium Sized Gas Cooled Fast Reactor with Natural Uranium as Fuel Cycle Input

2010 ◽  
Author(s):  
Meriyanti ◽  
Zaki Su’ud ◽  
K. Rijal ◽  
Zuhair ◽  
A. Ferhat ◽  
...  
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Natural Uranium ◽  
Preliminary Design ◽  
Design Study

scholarly journals Design of Gas-Cooled Fast Reactor 600MWth with Natural Uranium As Fuel Circle Input

2013 ◽  
Vol 14 (1) ◽  
pp. 11 ◽  
Author(s):  
Menik Ariani ◽  
Zaki Su’ud ◽  
Fiber Monado
Keyword(s):  
Fast Reactor ◽  
Power Distribution ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Thermal Power ◽  
Economic Value ◽  
Natural Uranium ◽  
Energy Group ◽  
Study Results ◽  
Macroscopic Cross Section

This article presents the conceptual design of gas-cooled fast reactor (helium), the small size of the long-lived 600 MWth. Early stages of the design is to determine the geometry of the terrace, the value of the volume fraction and the mass fraction of fuel, cladding and coolant structure to calculate the parameters of reactivity, burnup, power distribution and density changes nuclides U238 and Pu239. The calculation is done using SRAC-CITATION code. SRAC code with JENDL-3.2 Data nuclides produced macroscopic cross section values for the eight energy group. Multi-group numerical solution of diffusion equations for 2-D geometry terrace RZ performed by CITATION code. The study results showed that the scheme Modified CANDLE, thermal power output is 600 MWth, with a fuel cycle for 10 years. This reactor has the advantage of requiring only the input of natural uranium in the fuel cycle, without the need for enrichment processes that affect the economic value. Keywords : Reactor, natural uranium, modified candle, burnup

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.

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

Current Status of the Development of the Fast Reactor Fuel Cycle in India

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Current Status ◽  
Fast Reactor Fuel
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