Thermodynamic Modelling of the Uranium-Carbon-Oxygen System in the Frame of the Uranium Oxide and Carbon Interaction in the TRISO Fuel Particle of High Temperature Reactor

2006 ◽  
pp. 1944-1951
Author(s):  
Jean Christophe Dumas ◽  
Jean Paul Piron ◽  
Sylvie Chatain ◽  
Christine Guéneau
Keyword(s):  
High Temperature ◽  
Uranium Oxide ◽  
Thermodynamic Modelling ◽  
Fuel Particle ◽  
Triso Fuel ◽  
Oxygen System ◽  
High Temperature Reactor

scholarly journals Computational Model for the Neutronic Simulation of Pebble Bed Reactor’s Core Using MCNPX

2014 ◽  
Vol 2014 ◽  
pp. 1-12 ◽  
Author(s):  
J. Rosales ◽  
A. Muñoz ◽  
C. García ◽  
L. García ◽  
C. Brayner ◽  
...  
Keyword(s):  
High Temperature ◽  
Computational Model ◽  
Inherent Safety ◽  
Pebble Bed ◽  
Pebble Bed Reactor ◽  
Triso Fuel ◽  
Very High Temperature Reactor ◽  
Fuel Design ◽  
High Temperature Reactor ◽  
Very High

Very high temperature reactor (VHTR) designs offer promising performance characteristics; they can provide sustainable energy, improved proliferation resistance, inherent safety, and high temperature heat supply. These designs also promise operation to high burnup and large margins to fuel failure with excellent fission product retention via the TRISO fuel design. The pebble bed reactor (PBR) is a design of gas cooled high temperature reactor, candidate for Generation IV of Nuclear Energy Systems. This paper describes the features of a detailed geometric computational model for PBR whole core analysis using the MCNPX code. The validation of the model was carried out using the HTR-10 benchmark. Results were compared with experimental data and calculations of other authors. In addition, sensitivity analysis of several parameters that could have influenced the results and the accuracy of model was made.

Thermodynamic Modelling of the Uranium-Carbon-Oxygen System in the Frame of the Uranium Oxide and Carbon Interaction in the TRISO Fuel Particle of High Temperature Reactor

2006 ◽  
Vol 45 ◽  
pp. 1944-1951 ◽  
Author(s):  
Jean Christophe Dumas ◽  
Jean Paul Piron ◽  
Sylvie Chatain ◽  
Christine Guéneau
Keyword(s):  
High Temperature ◽  
Fission Products ◽  
Nuclear Materials ◽  
Chemical Compositions ◽  
Fuel Particle ◽  
Chemical Systems ◽  
Triso Fuel ◽  
Physico Chemical ◽  
Chemical Studies ◽  
Fuel Particles

A thermodynamic approach is necessary in order to predict and understand physico-chemical phenomena occurring in nuclear materials under irradiation, involving large chemical systems with a lot of elements including both initial nuclides and fission products (FP). In the frame of thermo-chemical studies of the High Temperature Reactors fuel, a first step is to assess the (U-O-C) system in order to understand the interaction between the UO2 kernel and the pyrocarbon layers constituting such a fuel particle. Our model for irradiated oxide fuel, based on Lindemer’s analysis, has been improved by introducing the (U-O-C) model developed by C. Guéneau & al into the SAGE code. Chemical compositions and related carbon oxides pressures of irradiated TRISO fuel particles have been calculated with the data published by Minato & al. We discuss our results by comparison with their thermochemical calculations and with their experimental observations. This approach can be used to predict the behaviour of complex nuclear materials, especially for the different kind of fuel materials considered in the frame of Gas Fast Reactors.

Fabrication of uniform ZrC coating layer for the coated fuel particle of the very high temperature reactor

2008 ◽  
Vol 376 (2) ◽  
pp. 146-151 ◽  
Author(s):  
Shohei Ueta ◽  
Jun Aihara ◽  
Atsushi Yasuda ◽  
Hideharu Ishibashi ◽  
Tomoo Takayama ◽  
...  
Keyword(s):  
High Temperature ◽  
Coating Layer ◽  
Fuel Particle ◽  
Very High Temperature Reactor ◽  
High Temperature Reactor ◽  
Coated Fuel Particle ◽  
Zrc Coating ◽  
Very High

Two-Dimensional Full Core Analysis of IFBA-Coated TRISO Fuel Particles in Very High Temperature Reactors

2020 ◽  
Author(s):  
Mohammad Alrwashdeh ◽  
Saeed A. Alameri
Keyword(s):  
Monte Carlo ◽  
High Temperature ◽  
Coating Layer ◽  
Reactor Core ◽  
Two Dimensional ◽  
Triso Fuel ◽  
High Temperature Reactor ◽  
Reactor Type ◽  
Very High ◽  
Full Core

Abstract The Prismatic-core Advanced High Temperature Reactor (PAHTR) is a very high temperature reactor type which is one of promising reactor type technologies classified as Generation IV by the International Forum. The new technology designs are identified as being proliferation resistant, safe, economical, efficient, and long fuel cycle. In this paper, the continuous-energy Monte Carlo method is capable of capturing all of the necessary reactor physics parameters using high fidelity two dimensional model with Serpent Monte Carlo code, and applied for a large scale reactor core loaded with TRi-structural ISOtropic (TRISO) particle by taking into account the double heterogeneity effect. These analyses were performed for PAHTR reactor core that utilizes TRISO particles fuel embedded in graphite matrix by applying a new innovative idea of adding Integral Fuel Burnable Absorber (IFBA) as an additional coating layer with a designated thickness. Adding IFBA coating could lead to compressed excess reactivity at the Beginning of Cycle (BOC), and extended burnup cycle. The additional IFBA coating layer is placed in the outer surface of the fuel kernel and covered by the buffer layers that compose the TRISO fuel particle. Neutronic calculations were performed for both TRISO particle unit cell and for full core with homogenous distribution of IFBA coating.

Requirements for high temperature reactor fuel particle design assessment

2001 ◽  
Vol 38 (3-4) ◽  
pp. 415-418 ◽  
Author(s):  
Ph. Chapelot ◽  
A. Languille ◽  
X. Raepsaet ◽  
D. Hittner
Keyword(s):  
High Temperature ◽  
Reactor Fuel ◽  
Fuel Particle ◽  
Design Assessment ◽  
High Temperature Reactor

Materials Modeling - a key for the Design of Advanced High Temperature Reactor Components

2007 ◽  
pp. 50-57
Author(s):  
Maria Samaras ◽  
Wolfgang Hoffelner ◽  
Chu Chun Fu ◽  
Michel Guttmann ◽  
Roger E. Stoller
Keyword(s):  
High Temperature ◽  
Materials Modeling ◽  
High Temperature Reactor
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