Towards a Monte Carlo simulation of a pebble bed type high temperature gas cooled reactor using Geant4

2021 ◽  
pp. 108868
Author(s):  
A.C. Cilliers ◽  
S.H. Connell ◽  
J. Conradie ◽  
M.N.H. Cook ◽  
M. Laassiri ◽  
...  
Keyword(s):  
Monte Carlo Simulation ◽  
Monte Carlo ◽  
High Temperature ◽  
Pebble Bed ◽  
High Temperature Gas

scholarly journals Prediction calculations for the first criticality of the HTR-PM using the PANGU code

2021 ◽  
Vol 32 (9) ◽  
Author(s):  
Ding She ◽  
Bing Xia ◽  
Jiong Guo ◽  
Chun-Lin Wei ◽  
Jian Zhang ◽  
...  
Keyword(s):  
Monte Carlo ◽  
High Temperature ◽  
Power Plant ◽  
Uncertainty Analysis ◽  
Nuclear Data ◽  
High Fidelity ◽  
Pebble Bed ◽  
Input Model ◽  
High Temperature Reactor ◽  
High Temperature Gas

AbstractThe high-temperature reactor pebble-bed module (HTR-PM) is a modular high-temperature gas-cooled reactor demonstration power plant. Its first criticality experiment is scheduled for the latter half of 2021. Before performing the first criticality experiment, a prediction calculation was performed using PANGU code. This paper presents the calculation details for predicting the HTR-PM first criticality using PANGU, including the input model and parameters, numerical results, and uncertainty analysis. The accuracy of the PANGU code was demonstrated by comparing it with the high-fidelity Monte Carlo solution, using the same input configurations. It should be noted that keff can be significantly affected by uncertainties in nuclear data and certain input parameters, making the criticality calculation challenge. Finally, the PANGU is used to predict the critical loading height of the HTR-PM first criticality under design conditions, which will be evaluated in the upcoming experiment later this year.

The Modelling and Coupling Methodology of ANSYS CFX Using Porous Media for PB-AHTR

2013 ◽  
Author(s):  
Linsen Li ◽  
Haomin Yuan ◽  
Kan Wang
Keyword(s):  
Porous Media ◽  
Monte Carlo ◽  
Steady State ◽  
High Temperature ◽  
Monte Carlo Code ◽  
First Principle ◽  
Pebble Bed ◽  
Coupled Calculation ◽  
Ansys Cfx ◽  
High Temperature Reactor

This paper introduces a first-principle steady-state coupling methodology using the Monte Carlo Code RMC and the CFD code CFX which can be used for the analysis of small and medium reactors. The RMC code is used for neutronics calculation while CFX is used for Thermal-Hydraulics (T-H) calculation. A Pebble Bed-Advanced High Temperature Reactor (PB-AHTR) core is modeled using this method. The porous media is used in the CFX model to simulate the pebble bed structure in PB-AHTR. This research concludes that the steady-state coupled calculation using RMC and CFX is feasible and can obtain stable results within a few iterations.

Steady-State Neutrbnic Investigations to the Accident of Water Ingress in Systems with Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel

1987 ◽  
Vol 97 (1) ◽  
pp. 72-88 ◽  
Author(s):  
F. Schürrer ◽  
W. Ninaus ◽  
K. Oswald ◽  
R. Rabitsch ◽  
Hj. Müller ◽  
...  
Keyword(s):  
Steady State ◽  
High Temperature ◽  
Reactor Fuel ◽  
Pebble Bed ◽  
Water Ingress ◽  
High Temperature Gas

scholarly journals A review of pebble flow study for pebble bed high temperature gas-cooled reactor

2019 ◽  
Vol 1 (3) ◽  
pp. 159-176 ◽  
Author(s):  
Shengyao Jiang ◽  
Jiyuan Tu ◽  
Xingtuan Yang ◽  
Nan Gui
Keyword(s):  
High Temperature ◽  
Pebble Bed ◽  
Pebble Flow ◽  
Flow Study ◽  
High Temperature Gas

Carbon materials in a high temperature gas-cooled reactor pebble-bed module

2018 ◽  
Vol 33 (2) ◽  
pp. 97-108 ◽  
Author(s):  
Xiang-wen Zhou ◽  
Yang Yang ◽  
Jing Song ◽  
Zhen-ming Lu ◽  
Jie Zhang ◽  
...  
Keyword(s):  
High Temperature ◽  
Carbon Materials ◽  
Pebble Bed ◽  
High Temperature Gas
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