Current status of the feasibility study on commercialized fast reactor cycle systems and reactor core performance of the promising fast reactors [Progress in Nuclear Energy 47 (2005) 300–313]

2006 ◽  
Vol 48 (2) ◽  
pp. 185
Author(s):  
Shoji Kotake ◽  
Yoshihiko Sakamoto ◽  
Yutaka Sagayama
2005 ◽  
Vol 47 (1-4) ◽  
pp. 300-313 ◽  
Author(s):  
Shoji Kotake ◽  
Yoshihiko Sakamoto ◽  
Yutaka Sagayama

2021 ◽  
Vol 2072 (1) ◽  
pp. 012002
Author(s):  
Z Su’ud ◽  
N R Galih ◽  
M Ariani

Abstract Human need of energy will increase time to time. Therefore, a safe, renewable, and efficient source of energy, which is Nuclear Energy, is needed. Nuclear Power Plant (NPP) is the most compatible solution to provide electricity to human race in the future. The problem that came within NPP is the danger of proliferation issues. The method that has been developed to overcome this problem is CANDLE [5] and has been modified by Prof. Zaki Su’ud (Modified CANDLE scheme). This research use Axial Modified CANDLE Scheme to Helium-Cooled Fast Reactor with Natural Uranium Carbide-Thorium Carbide as fuel and applied to various size of core as optimization. Neutronic aspect such as, burn up level, multiplication factor, and conversion ratio are utilized in this paper in order to analyse the behaviour of the reactor. Other than that, percentage of Uranium has been varied to reduce power peaking. The neutronic calculation has been done using SRAC and core design calculation by FI-ITB-CH1. This research concludes that power peaking reduction is able to achieve by combining Uranium Carbide and Thorium Carbide to the fuel. The optimum reactor design reached at 360 cm of core radius and 303 cm of core height.


Author(s):  
Yuuichi Tooya ◽  
Tadahiro Washiya ◽  
Kenji Koizumi ◽  
Shinichi Morita

Japan Atomic Energy Agency (JAEA) has been leading feasibility study on commercialized fast reactor cycle systems in Japan. In this study, we have proposed a new disassembly technology by mechanical disassembly system that consists of a mechanical cutting step and a wrapper tube pulling step. In the mechanical disassembly system, high durability mechanical tool grinds the wrapper tube (Slit-cut (S/C) operation in circle direction), and then the wrapper tube is pulled out and removed from the fuel assembly. Then the fuel pins are cut (Crop-cut (C/C) operation at entrance nozzle side) and the entrance nozzle is removed. The fuel pins are transported to the shearing device in next process. The Fundamental tests were carried out with simulated FBR fuel pins and wrapper tube, and cutting performance and wrapper tube pulling performance has been confirmed by engineering scale. As results, we established an efficient disassembly procedure and the fundamental design of mechanical disassembly system.


Author(s):  
Gregory M. Cartland-Glover ◽  
Stefano Rolfo ◽  
Alex Skillen ◽  
David R. Emerson ◽  
Charles Moulinec ◽  
...  

Molten salt reactors are a very promising option for the development of highly innovative solutions for the nuclear energy production of the future. The techniques used to model thermal hydraulics of a molten salt fast reactor when frozen salt wall technology is applied to the core vessel wall are presented here for 2D numerical models of a hyperboloid reactor core region with a heat exchanger was applied in Code_Saturne. A 3D simulation of the fluid flow and heat transfer with 16 recirculation loops containing the heat exchangers is also presented. It was found that there is strong cooling in separated flow regions in the external heat exchanger, which freezes where the porous model is applied.


2017 ◽  
Vol 131 ◽  
pp. 86-93 ◽  
Author(s):  
Keiko Chitose ◽  
Hiroyasu Mochizuki ◽  
Naoyuki Takaki

2002 ◽  
Vol 40 (3-4) ◽  
pp. 607-613
Author(s):  
Kazuo Arie ◽  
Masao Suzuki ◽  
Masatoshi Kawashima ◽  
Satoshi Moro ◽  
Masaki Saito ◽  
...  

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj

Sign in / Sign up

Export Citation Format

Share Document