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

Author(s):  
Meriyanti ◽  
Zaki Su’ud ◽  
K. Rijal ◽  
Zuhair ◽  
A. Ferhat ◽  
...  
2014 ◽  
Author(s):  
Fiber Monado ◽  
Menik Ariani ◽  
Zaki Su'ud ◽  
Abdul Waris ◽  
Khairul Basar ◽  
...  

2004 ◽  
Vol 41 (3) ◽  
pp. 307-314 ◽  
Author(s):  
Takeshi TAKATA ◽  
Yoshikazu KOMA ◽  
Koji SATO ◽  
Masayoshi KAMIYA ◽  
Atsuhiro SHIBATA ◽  
...  

Author(s):  
Takeshi Takata ◽  
Yoshikazu Koma ◽  
Koji Sato ◽  
Masayoshi Kamiya ◽  
Atsuhiro Shibata ◽  
...  

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

1993 ◽  
Vol 140 (2) ◽  
pp. 251-260 ◽  
Author(s):  
Zaki Su'ud ◽  
Hiroshi Sekimoto

2012 ◽  
Author(s):  
Menik Ariani ◽  
Zaki Su’ud ◽  
Abdul Waris ◽  
Khairurrijal ◽  
Fiber Monado ◽  
...  

2013 ◽  
Vol 14 (1) ◽  
pp. 11 ◽  
Author(s):  
Menik Ariani ◽  
Zaki Su’ud ◽  
Fiber Monado

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


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.


Sign in / Sign up

Export Citation Format

Share Document