Two-Dimensional Calculation of Neutron Flux and Power Distribution in the Fuel Assembly of a Light Water Reactor

1988 ◽  
Vol 100 (3) ◽  
pp. 260-268 ◽  
Author(s):  
Zhao Chunlei ◽  
Xie Zhongsheng ◽  
Yin Banghua
2015 ◽  
Vol 1 (4) ◽  
Author(s):  
Wenzhong Zhou ◽  
Rong Liu

Oxygen redistribution with a high-temperature gradient is an important fuel performance concern in fast-breeder reactor (FBR) and light-water reactor (LWR) (U,Pu)O2 fuel under irradiation, and affects fuels properties, power distribution, and fuel overall performance. This paper studies the burnup dependent oxygen and heat diffusion behavior in a fully coupled way within (U,Pu)O2 FBR and LWR fuels. The temperature change shows relatively larger impact on oxygen to metal (O/M) ratio redistribution rather than O/M ratio change on temperature, whereas O/M ratio redistributions show different trends for FBR and LWR fuels due to their different deviations from the stoichiometry of oxygen under high-temperature environments.


1990 ◽  
Vol 90 (2) ◽  
pp. 191-204 ◽  
Author(s):  
Hermann Würz ◽  
Werner Eyrich ◽  
Hans-Joachim Becker

2010 ◽  
Vol 172 (2) ◽  
pp. 132-142 ◽  
Author(s):  
Sadao Uchikawa ◽  
Tsutomu Okubo ◽  
Yoshihiro Nakano

2015 ◽  
Vol 2015 ◽  
pp. 1-8
Author(s):  
Haileyesus Tsige-Tamirat ◽  
Luca Ammirabile

Hydride fuels have features which could make their use attractive in future advanced power reactors. The potential benefit of use of hydride fuel in HPLWR without introducing significant modification in the current core design concept of the high-performance light water reactor (HPLWR) has been evaluated. Neutronics and thermal hydraulic analyses were performed for a single assembly model of HPLWR with oxide and hydride fuels. The hydride assembly shows higher moderation with softer neutron spectrum and slightly more uniform axial power distribution. It achieves a cycle length of 18 months with sufficient excess reactivity. At Beginning of Cycle the fuel temperature coefficient of the hydride assembly is higher whereas the moderator and void coefficients are lower. The thermal hydraulic results show that the achievable fuel temperature in the hydride assembly is well below the design limits. The potential benefits of the use of hydride fuel in the current design of the HPLWR with the achieved improvements in the core neutronics characteristics are not sufficient to justify the replacement of the oxide fuel. Therefore for a final evaluation of the use of hydride fuels in HPLWR concepts additional studies which include modification of subassembly and core layout designs are required.


1994 ◽  
Vol 153 (1) ◽  
pp. 71-86 ◽  
Author(s):  
K. Shibata ◽  
T. Isozaki ◽  
S. Ueda ◽  
R. Kurihara ◽  
K. Onizawa ◽  
...  

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