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

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.

A Procedure for the Pre-Conceptual Design of Fast Reactors and Application to a Gas-Cooled Sub-Critical Transmuter

2014 ◽  
Author(s):  
Carlo Fiorina ◽  
Konstantin Mikityuk ◽  
Jiři Křepel
Keyword(s):  
Conceptual Design ◽  
Fast Reactor ◽  
Power Distribution ◽  
Fuel Cycle ◽  
Reactor Core ◽  
Maximum Pressure ◽  
Test Case ◽  
Pressure Losses ◽  
Design And Optimization ◽  
Inert Matrix

A C++ procedure has been developed for the design and optimization of Fast Reactor (FR) cores. It couples the ERANOS based EQL3D procedure developed at PSI for FR equilibrium fuel cycle analysis with a dedicated MATLAB script that evaluates the thermal-hydraulic characteristics of the reactor core. It is conceived to investigate reactors with both standard pins and annular pins. The procedure accepts as input the physical properties of the system, as well as a set of target core parameters presently consisting of core power, maximum fuel burnup, multiplication factor, inner pin diameter (for annular pins) or maximum pressure losses (for standard pins), and core height. It gives as a result a core design fulfilling these design objectives and meeting the constraints on maximum fuel and clad temperatures. In case of annular pins, it also equalizes the temperature rise inside and outside of the core average pin. The procedure considers the possibility of two-zone cores and adjusts the fuel composition in the two zones to achieve an optimal radial power distribution. Finally, it can evaluate safety parameters and fuel cycle characteristics both at beginning-of-life and at equilibrium. As a test case, the procedure has been used for the pre-conceptual design of a sub-critical Gas Fast Reactor core employing inert-matrix sphere-pac fuel and annular pins with SiC cladding.

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 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

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

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.

Desain Study of Pb-Bi Cooled Fast Reactors with Natural Uranium as Fuel Cycle Input Using Special Shuffling Strategy in Radial Direction

2013 ◽  
Vol 772 ◽  
pp. 530-535 ◽  
Author(s):  
Zaki Su’ud ◽  
Feriska H. Irka ◽  
Taufiq Imam ◽  
H. Sekimoto ◽  
P. Sidik
Keyword(s):  
Power Distribution ◽  
Fuel Cycle ◽  
Batch Reactor ◽  
Operation Time ◽  
Axial Direction ◽  
Natural Uranium ◽  
Fast Reactors ◽  
Uranium Fuel ◽  
Slow Growing ◽  
Effective Multiplication

Design study of Pb-Bi cooled fast reactors with natural uranium as fuel cycle input using special radial shuffling strategy has been performed. The reactors utilizes UN-PUN as fuel, Eutectic Pb-Bi as coolant, and can be operated without refueling for 10 years in each batch. Reactor design optimization is performed to utilize natural uranium as fuel cycle input. This reactor subdivided into 6 regions with equal volume in radial directions. The natural uranium is initially put in region 1, and 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. The calculation has been done by using SRAC-Citation system code and JENDL-3.2 library. The effective multiplication factor change increases monotonously during 10 years reactor operation time. There is significant power distribution change in the central part of the core during the BOC and the EOC. It is larger than that in the case of modified CANDLE case which use axial direction burning region move. The burnup level of fuel is slowly grows during the first 15 years but then grow fastly in the rest of burnup history. This pattern is a little bit different from the case of modified CANDLE burnup scheme in Axial direction in which the slow growing burnup period is relatively longer almost half of the burnup history.

Burnup Computation for HTR-10 Using Layer-to-Layer Movement

2013 ◽  
Author(s):  
Shang-Chien Wu ◽  
Rong-Jiun Sheu ◽  
Jinn-Jer Peir ◽  
Jenq-Horng Liang
Keyword(s):  
Power Distribution ◽  
Fuel Cycle ◽  
Volume Fraction ◽  
Reactor Core ◽  
Operation Time ◽  
Axial Direction ◽  
Bottom Layer ◽  
Movement Model ◽  
Cycle Number ◽  
The Core

This study proposes a layer-to-layer movement model using a once-through fuel cycle strategy to dynamically simulate the on-line refueling process employed in HTR-10. The MCNPX 2.6.0 computer code and continuous energy data library ENDF/B-VII were used in performing all of the computations. In this study, the pebble bed in the core was equally divided into five layers in the axial direction, and the volume fractions of the fuel and graphite pebbles in the initial core were 0.57 and 0.43, respectively. After each fuel cycle, the bottom layer was discharged from the core and discarded while a new layer containing only fuel pebbles was added to the top layer of the core. Hence, the volume fraction of the fuel pebbles increased with greater operation time. This study further proposes that each fuel cycle is stopped to initiate the refueling process for next fuel cycle whenever the effective multiplication factor (keff) reaches approximately 1.005. The results revealed that spikes in the keff versus reactor operation time are the result of burnup and refueling. The fuel cycle tends to approach an equilibrium cycle after refueling five times. In addition, the axial power distribution tends to change from a bottom-peaked to a top-peaked phenomenon as the fuel cycle number increases. In essence, the axial power distribution is nearly un-changed once the reactor core reaches an equilibrium cycle. This phenomenon is also verified by the corresponding axial burnup distribution, average burnup, and mass of special nuclides as a function of operation time.

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