scholarly journals GEN-IV Benchmarking of Triso Fuel Performance Models under accident conditions modeling input data

2016 ◽  
Author(s):  
Blaise Paul Collin
Keyword(s):  
Input Data ◽  
Performance Models ◽  
Fuel Performance ◽  
Triso Fuel ◽  
Gen Iv ◽  
Accident Conditions

Preliminary Development of a TRISO Fuel Performance Analysis Code: FFAT

2018 ◽  
Author(s):  
Jian Li ◽  
Ding She ◽  
Lei Shi ◽  
Jing Zhao
Keyword(s):  
Performance Analysis ◽  
Mechanical Performance ◽  
Performance Model ◽  
Fuel Performance ◽  
Triso Fuel ◽  
Coated Particle ◽  
First Results ◽  
Fuel Particles ◽  
Accident Conditions ◽  
Radioactivity Retention

Tristructural isotropic (TRISO) fuel particles are chosen as the major fuel type of High temperature gas cooled reactor (HTGR). The TRISO coated particle also acts as the first barrier for radioactivity retention. The performance of the TRISO coated particle has a significant influence on the safety of HTGR. A set of fuel performance analysis codes have been developed during the past decades. The main functions of these codes are conducting stress calculation and failure probability prediction. PANAMA is a widely used German version fuel performance analysis code, which simulates the mechanical performance of TRISO coated particle under normal and accident conditions. In this code, only a simple pressure vessel model is considered, which is insufficient in stress analysis and fuel failure rate prediction. Nowadays, efforts have been done to update the fuel performance model utilized in PANAMA code, and a new TRISO fuel performance analysis code, FFAT, is under developed. This paper describes the newly updated TRISO fuel performance model and presents some first results based on the updated model.

A review of TRISO fuel performance models

2010 ◽  
Vol 405 (1) ◽  
pp. 74-82 ◽  
Author(s):  
Jeffrey J. Powers ◽  
Brian D. Wirth
Keyword(s):  
Performance Models ◽  
Fuel Performance ◽  
Triso Fuel

A review of TRISO-coated particle nuclear fuel performance models

Rare Metals ◽  
2006 ◽  
Vol 25 (6) ◽  
pp. 337-342 ◽  
Author(s):  
B LIU ◽  
T LIANG ◽  
C TANG
Keyword(s):  
Nuclear Fuel ◽  
Performance Models ◽  
Fuel Performance ◽  
Coated Particle

Extending the application range of a fuel performance code from normal operating to design basis accident conditions

2008 ◽  
Vol 383 (1-2) ◽  
pp. 137-143 ◽  
Author(s):  
P. Van Uffelen ◽  
C. Győri ◽  
A. Schubert ◽  
J. van de Laar ◽  
Z. Hózer ◽  
...  
Keyword(s):  
Fuel Performance ◽  
Application Range ◽  
Normal Operating ◽  
Design Basis ◽  
Design Basis Accident ◽  
Accident Conditions

Fission Product Release From HTGR Fuel Under Core Heatup Accident Conditions

2008 ◽  
Author(s):  
Karl Verfondern ◽  
Heinz Nabielek
Keyword(s):  
Fission Product ◽  
Technology Development ◽  
Normal Operation ◽  
Fuel Performance ◽  
Heating Facility ◽  
Product Release ◽  
Essential Input ◽  
Accident Conditions ◽  
Product Species ◽  
Htgr Fuel

Various countries engaged in the development and fabrication of modern fuel for the High Temperature Gas-Cooled Reactor (HTGR) have initiated activities of modeling the fuel and fission product release behavior with the aim of predicting the fuel performance under operating and accidental conditions of future HTGRs. Within the IAEA directed Coordinated Research Project CRP6 on “Advances in HTGR Fuel Technology Development” active since 2002, the 13 participating Member States have agreed upon benchmark studies on fuel performance during normal operation and under accident conditions. While the former has been completed in the meantime, the focus is now on the extension of the national code developments to become applicable to core heatup accident conditions. These activities are supported by the fact that core heatup simulation experiments have been resumed recently providing new, highly valuable data. Work on accident performance will be — similar to the normal operation benchmark — consisting of three essential parts comprising both code verification that establishes the correspondence of code work with the underlying physical, chemical and mathematical laws, and code validation that establishes reasonable agreement with the existing experimental data base, but including also predictive calculations for future heating tests and/or reactor concepts. The paper will describe the cases to be studied and the calculational results obtained with the German computer model FRESCO. Among the benchmark cases in consideration are tests which were most recently conducted in the new heating facility KUEFA. Therefore this study will also re-open the discussion and analysis of both the validity of diffusion models and the transport data of the principal fission product species in the HTGR fuel materials as essential input data for the codes.

Multiphysics Analysis of Thorium-Based Fuel Performance Under Reactor Steady-State and Transient Accident

2020 ◽  
Author(s):  
Chenjie Qiu ◽  
Rong Liu ◽  
Wenzhong Zhou
Keyword(s):  
Steady State ◽  
Safety Margin ◽  
Operating Conditions ◽  
Fuel Performance ◽  
Transient Conditions ◽  
Normal Operating ◽  
Accident Conditions ◽  
Behavior Models ◽  
Line Temperature ◽  
Thermal Physical Properties

Abstract The ThO2 fuel has higher thermal conductivity and melting boiling point than the UO2 fuel, which is beneficial to the fast removal of heat and the improvement of fuel melt margin. In this paper, the material properties and thermodynamic behaviors of thorium-based fuel were firstly reviewed. And then the thermal physical properties and the fuel behavior models of Th0.923U0.077O2 fuel and Th0.923Pu0.077O2 fuel have been implemented in fuel performance analysis code FRAPCON and FRAPTRAN. Finally, the performances of Th0.923U0.077O2 fuel, Th0.923Pu0.077O2 fuel and UO2 fuel under both normal operating conditions and transient conditions (RIA and LOCA) are analyzed and compared. The Th0.923U0.077O2 fuel is found to have lower fuel center-line temperature and the thorium-based fuels are observed to have a delayed pellet-cladding mechanical interaction (PCMI) under steady state. Furthermore, the fission gas release, cladding strain and internal fuel energy under transient conditions are found to be lower too. Lastly, the cladding displacement and temperature under transient conditions are also compared. The thorium-based fuel was found to have a higher safety margin and accident resistance than conventional UO2 fuel under both normal operating conditions and accident conditions.

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