scholarly journals Suggested Failure Probability Calculation Method for Japanese High-Quality High-Temperature Gas-Cooled Reactor (HTGR) Fuel

2012 ◽  
Vol 11 (2) ◽  
pp. 158-163 ◽  
Author(s):  
Jun AIHARA ◽  
Shohei UETA ◽  
Taiju SHIBATA ◽  
Kazuhiro SAWA
Keyword(s):  
High Temperature ◽  
Failure Probability ◽  
Calculation Method ◽  
High Quality ◽  
Probability Calculation ◽  
High Temperature Gas ◽  
Htgr Fuel

Comparative Study of GaN Growth Process by MOVPE

1999 ◽  
Vol 572 ◽  
Author(s):  
Jingxi Sun ◽  
J. M. Redwing ◽  
T. F. Kuech
Keyword(s):  
High Temperature ◽  
Comparative Study ◽  
Gas Phase ◽  
Residence Time ◽  
Gas Flow ◽  
Flow Sheet ◽  
Flow Zone ◽  
High Quality ◽  
Phase Temperature ◽  
High Temperature Gas

ABSTRACTA comparative study of two different MOVPE reactors used for GaN growth is presented. Computational fluid dynamics (CFD) was used to determine common gas phase and fluid flow behaviors within these reactors. This paper focuses on the common thermal fluid features of these two MOVPE reactors with different geometries and operating pressures that can grow device-quality GaN-based materials. Our study clearly shows that several growth conditions must be achieved in order to grow high quality GaN materials. The high-temperature gas flow zone must be limited to a very thin flow sheet above the susceptor, while the bulk gas phase temperature must be very low to prevent extensive pre-deposition reactions. These conditions lead to higher growth rates and improved material quality. A certain range of gas flow velocity inside the high-temperature gas flow zone is also required in order to minimize the residence time and improve the growth uniformity. These conditions can be achieved by the use of either a novel reactor structure such as a two-flow approach or by specific flow conditions. The quantitative ranges of flow velocities, gas phase temperature, and residence time required in these reactors to achieve high quality material and uniform growth are given.

scholarly journals A Failure Probability Calculation Method for Power Equipment Based on Multi-Characteristic Parameters

Energies ◽  
2017 ◽  
Vol 10 (5) ◽  
pp. 704 ◽  
Author(s):  
Hang Liu ◽  
Youyuan Wang ◽  
Yi Yang ◽  
Ruijin Liao ◽  
Yujie Geng ◽  
...  
Keyword(s):  
Failure Probability ◽  
Calculation Method ◽  
Power Equipment ◽  
Characteristic Parameters ◽  
Probability Calculation

High-speed, high-quality crystal growth of 4H-SiC by high-temperature gas source method

2014 ◽  
Vol 7 (6) ◽  
pp. 065502 ◽  
Author(s):  
Norihiro Hoshino ◽  
Isaho Kamata ◽  
Yuichiro Tokuda ◽  
Emi Makino ◽  
Naohiro Sugiyama ◽  
...  
Keyword(s):  
Crystal Growth ◽  
High Temperature ◽  
High Speed ◽  
High Quality ◽  
Source Method ◽  
Gas Source ◽  
High Temperature Gas

Development of high temperature gas-cooled reactor (HTGR) fuel in Japan

2011 ◽  
Vol 53 (7) ◽  
pp. 788-793 ◽  
Author(s):  
Shohei Ueta ◽  
Jun Aihara ◽  
Kazuhiro Sawa ◽  
Atsushi Yasuda ◽  
Masaki Honda ◽  
...  
Keyword(s):  
High Temperature ◽  
High Temperature Gas ◽  
Htgr Fuel

scholarly journals Simulation of the HTR-10 Operation History With the PANGU Code

2021 ◽  
Vol 9 ◽  
Author(s):  
Ding She ◽  
Fubing Chen ◽  
Bing Xia ◽  
Lei Shi
Keyword(s):  
High Temperature ◽  
Fuel Cycle ◽  
Outlet Temperature ◽  
Reactor Physics ◽  
Important Data ◽  
Analysis And Design ◽  
Reactor Test ◽  
Test Module ◽  
High Temperature Gas ◽  
Htgr Fuel

The 10 MW High Temperature Gas-cooled Reactor-Test Module (HTR-10) is the first High Temperature Gas-cooled Reactor (HTGR) in China, which was operated from January 2003 to May 2007. The HTR-10 operation history provides very important data for the validation of HTGR codes. In this paper, the HTR-10 operation history is simulated with the PANGU code, which has been recently developed for HTGR reactor physics analysis and design. Models and parameters are constructed based on the measured data of the actual conditions. The simulation results agree well with the measurements in all steady-state power periods. The discrepancy of keff is generally below 0.5%, and the discrepancy of coolant outlet temperature is generally below 5°C. It is also figured out that the burnup of graphite impurities has considerable influence on the keff at the end of the operation history, which can cause over 1.5% discrepancy when neglecting the burnup of graphite impurities. By this work, the PANGU code’s applicability in actual HTGR fuel cycle simulations is demonstrated.

scholarly journals Study on the Implementation of Quality Assurance Aspect on High-Temperature Gas Cooled Reactor (HTGR)

2021 ◽  
Vol 2048 (1) ◽  
pp. 012022
Author(s):  
Sunarto ◽  
Sigit Santosa ◽  
Khusnul Khotimah ◽  
Sriyana
Keyword(s):  
Quality Assurance ◽  
High Temperature ◽  
Customer Requirements ◽  
Double Barrier ◽  
Quality Management Systems ◽  
Fuel Elements ◽  
Technological Analysis ◽  
Term Analysis ◽  
High Temperature Gas ◽  
Htgr Fuel

Abstract High-Temperature Gas Cooled Reactor (HTGR) Power Reactors have a layered safety system with the concept of a double barrier system. However, quality assurance is required to ensure the fulfillment of technological analysis weightings on power chamber materials, power ratings, fabrication components of High- Temperature Gas Cooled Reactor (HTGR) fuel elements, primary and secondary coolant pressures to meet customer requirements and be carried out continuously systematic and objective. This study analyzes the application of quality assurance, safety, security, the correctness of test/calibration results, increasing competitiveness, consumer protection and building trust (brand image) in the use of HTGR reactors to provide a reliable level of safety and security. The study method used is based on the literature review. The output of this study is the document of the HTGR reactor quality assurance systems to fulfill the IAEA-TECDOC-1645 requirements according to safety and standardization in frameworks design, material, fuel, and physical properties of the quality management systems. HTGR reactor has technical qualification, good performance of HTGR fuel, safety and accident analysis source term analysis, control of multi-modular HTGR and related human factor analysis, also optimizing radiation protection of HTGR

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