Neutronics, thermal-hydraulics, and multi-physics benchmark models for a generic pebble-bed fluoride-salt-cooled high temperature reactor (FHR)

2021 ◽  
Vol 384 ◽  
pp. 111461
Author(s):  
Nader Satvat ◽  
Fatih Sarikurt ◽  
Kevin Johnson ◽  
Ian Kolaja ◽  
Massimiliano Fratoni ◽  
...  
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
Thermal Hydraulics ◽  
Pebble Bed ◽  
High Temperature Reactor

Calculation of the Macroscopic Group Constant of Pebble Bed Fluoride Salt Cooled High Temperature Reactor Based on the Collision Probability Method

2017 ◽  
Author(s):  
Dida Zhang ◽  
Guobin Jia ◽  
Long He ◽  
Jiajie Shen ◽  
Zhichao Zhan ◽  
...  
Keyword(s):  
High Temperature ◽  
Complex Structure ◽  
Collision Probability ◽  
Probability Method ◽  
Fluoride Salt ◽  
Pebble Bed ◽  
Slowing Down ◽  
Group Constant ◽  
High Temperature Reactor ◽  
Integral Transport

The pebble bed fluoride salt cooled high temperature reactor (PB-FHR) is one of the generation IV nuclear reactors, a lot of study has concentrated on PB-FHR neutronics all over the world. As the most important part in the study work, the macroscopic group constant must be well prepared. The fuel pebble was chosen for the candidate of PB-FHR due to its outstanding, but the double heterogeneous due to its complex structure causes much difficult in the calculation of macroscopic group constant. In this work, an analytical program named Z2D is written to calculate the macroscopic group cross section. In the program, the collision probability method (CPM) was applied to solve the slowing-down integral transport equation, and the macroscopic constant was evaluated with the obtained neutron flux. Also, the recurrence method was introduced to accelerate the computing speed of slowing-down source. The results were compared with those calculated by MCNP, and good agreements were obtained.

scholarly journals Design Summary of the Mark-I Pebble-Bed, Fluoride Salt–Cooled, High-Temperature Reactor Commercial Power Plant

2016 ◽  
Vol 195 (3) ◽  
pp. 223-238 ◽  
Author(s):  
Charalampos Andreades ◽  
Anselmo T. Cisneros ◽  
Jae Keun Choi ◽  
Alexandre Y. K. Chong ◽  
Massimiliano Fratoni ◽  
...  
Keyword(s):  
High Temperature ◽  
Power Plant ◽  
Fluoride Salt ◽  
Pebble Bed ◽  
High Temperature Reactor

Uranium utilization with thorium blanket in Pebble Bed Fluoride salt-cooled high temperature reactor

2015 ◽  
Vol 83 ◽  
pp. 374-386 ◽  
Author(s):  
Guifeng Zhu ◽  
Yang Zou ◽  
Hongjie Xu ◽  
Ye Dai ◽  
Minghai Li ◽  
...  
Keyword(s):  
High Temperature ◽  
Fluoride Salt ◽  
Pebble Bed ◽  
High Temperature Reactor

Determination of Convective Heat Transfer Coefficients in the Core of the Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor Using Frequency Response Techniques

2017 ◽  
Author(s):  
Lakshana Huddar ◽  
Brandon Kuhnert ◽  
Ali James Albaaj ◽  
Connie Lee ◽  
Per F. Peterson
Keyword(s):  
Heat Transfer ◽  
Heat Transfer Coefficient ◽  
High Temperature ◽  
Transfer Coefficient ◽  
Test Section ◽  
Fluoride Salt ◽  
Transfer Coefficients ◽  
Pebble Bed ◽  
Heat Transfer Coefficients ◽  
High Temperature Reactor

Frequency response techniques have been historically used to characterize various reactor parameters. In this paper, we apply these techniques to the Pebble-Bed Fluoride-Salt-Cooled High Temperature Reactor (PB-FHR) in order to extract experimental values for the interfacial convective heat transfer coefficient in the pebble-bed reactor core. A test section is filled with randomly packed copper spheres and a simulant fluid is passed through it. The temperature of the fluid is made to vary at a given frequency, thereby affecting the temperature of the spheres in the test section as well. Using this data the heat transfer coefficient between the surface of the spheres and the fluid can be extracted. The preliminary results from these tests are shown in this paper along with the predicted heat transfer coefficients using the Wakao correlation for heat transfer in packed beds. The experiments were carried out for a range of Reynolds numbers from 250–500 and Prandtl numbers from 20 to 50. The Wakao correlation predicts the experiment fairly well. Generally, the experimental Nusselt numbers were found to exceed the predictions by up to 32%. An analytical solution for the solid and fluid temperatures in the test section is presented, and used to show the optimal frequency of oscillation for this experimental setup. This methodology can be used in the future to better characterize the dynamic response of coolant-boundary structures in the PB-FHR.

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