scholarly journals High Flux Isotope Reactor Low Enriched Uranium Low Density Silicide Fuel Design Parameters

2021 ◽  
Author(s):  
Benjamin Betzler ◽  
David Chandler ◽  
Jin Whan Bae ◽  
Germina Ilas ◽  
Jennifer Meszaros
2021 ◽  
Vol 2 (2) ◽  
pp. 207-214
Author(s):  
Thinh Truong ◽  
Heikki Suikkanen ◽  
Juhani Hyvärinen

In this paper, the conceptual design and a preliminary study of the LUT Heating Experimental Reactor (LUTHER) for 2 MWth power are presented. Additionally, commercially sized designs for 24 MWth and 120 MWth powers are briefly discussed. LUTHER is a scalable light-water pressure-channel reactor designed to operate at low temperature, low pressure, and low core power density. The LUTHER core utilizes low enriched uranium (LEU) to produce low-temperature output, targeting the district heating demand in Finland. Nuclear power needs to contribute to the decarbonizing of the heating and cooling sector, which is a much more significant greenhouse gas emitter than electricity production in the Nordic countries. The main principle in the development of LUTHER is to simplify the core design and safety systems, which, along with using commercially available reactor components, would lead to lower fabrication costs and enhanced safety. LUTHER also features a unique design with movable individual fuel assembly for reactivity control and burnup compensation. Two-dimensional (2D) and three-dimensional (3D) fuel assemblies and reactor cores are modeled with the Serpent Monte Carlo reactor physics code. Different reactor design parameters and safety configurations are explored and assessed. The preliminary results show an optimal basic core design, a good neutronic performance, and the feasibility of controlling reactivity by moving fuel assemblies.


Author(s):  
Hyeong Koo Kim ◽  
Sang Youn Jeon ◽  
Kyou Seok Lee ◽  
Jeong Ha Kim ◽  
Sang Jong Lee

The main objective of this study is to estimate the effects of some considerable fuel design parameters on the fluid elastic instability behavior of the fuel rod. For the estimation, 6 fuel design parameters which seem to have direct relation with fluid elastic instability behavior of the fuel rod have been selected and examined using the PLUS7 fuel rod for OPR1000 PWR plants in Korea. Those are fuel rod creep-down, spacer grid stiffness, spacer grid spring relaxation, inactive spacer grid spring, intermediate flow mixing grid effect and fuel rod damping. As a result, the fluid elastic instability factors are insensitive with spacer grid stiffness, relaxation and intermediate flow mixing grid effect, but the other parameters need to be controlled and evaluated appropriately to maintain stability with proper margins.


2007 ◽  
Author(s):  
Trent Primm ◽  
Ronald James Ellis ◽  
Jess C Gehin ◽  
Germina Ilas ◽  
James Henry Miller ◽  
...  

2015 ◽  
Author(s):  
Isaac T. Bodey ◽  
Franklin G. Curtis ◽  
Rao V. Arimilli ◽  
Kivanc Ekici ◽  
James D. Freels

2009 ◽  
Vol 162 (1) ◽  
pp. 87-97 ◽  
Author(s):  
Ned Xoubi ◽  
R. T. Primm ◽  
G. Ivan Maldonado

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