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

scholarly journals Analysis of Fission Products’ Release in Pebble-Bed High-Temperature Gas-Cooled Reactor Fuel Elements Using a Modified FRESCO II Numerical Model

2021 ◽  
Vol 2021 ◽  
pp. 1-8
Author(s):  
Chao Fang ◽  
Chuan Li ◽  
Jianzhu Cao ◽  
Ke Liu ◽  
Sheng Fang
Keyword(s):  
High Temperature ◽  
Source Term ◽  
Fission Products ◽  
Release Rates ◽  
Time Step ◽  
The Difference ◽  
Advanced Nuclear System ◽  
Fuel Elements ◽  
Term Analysis ◽  
High Temperature Gas

The radiation safety design and emergency analysis of an advanced nuclear system highly depends on the source term analysis results. In modular high-temperature gas-cooled reactors (HTGRs), the release rates of fission products (FPs) from fuel elements are the key issue of source term analysis. The FRESCO-II code has been established as a useful tool to simulate the accumulation and transport behaviors of FPs for many years. However, it has been found that the mathematical method of this code is not comprehensive, resulting in large errors for short-lived nuclides and large time step during calculations. In this study, we used the original model of TRISO particles and spherical fuel elements and provided a new method to amend the FRESCO-II code. The results show that, for long-lived radionuclides (Cs-137), the two methods are perfectly consistent with each other, while in the case of short-lived radionuclides (Cs-138), the difference can be more than 1%. Furthermore, the matrix method is used to solve the final release rates of FPs from fuel elements. The improved analysis code can also be applied to the source term analysis of other HTGRs.

Automatic X-ray inspection for escaped coated particles in spherical fuel elements of high temperature gas-cooled reactor

Energy ◽  
2014 ◽  
Vol 68 ◽  
pp. 385-398 ◽  
Author(s):  
Min Yang ◽  
Qi Liu ◽  
Hongsheng Zhao ◽  
Ziqiang Li ◽  
Bing Liu ◽  
...  
Keyword(s):  
High Temperature ◽  
Coated Particles ◽  
X Ray ◽  
Fuel Elements ◽  
High Temperature Gas

Wear behavior of graphitic matrix of fuel elements used in pebble-bed high-temperature gas-cooled reactors against steel

2018 ◽  
Vol 328 ◽  
pp. 353-358 ◽  
Author(s):  
Bin Wu ◽  
Yue Li ◽  
Hong-sheng Zhao ◽  
Shuang Liu ◽  
Bing Liu ◽  
...  
Keyword(s):  
High Temperature ◽  
Wear Behavior ◽  
Pebble Bed ◽  
Fuel Elements ◽  
High Temperature Gas

scholarly journals Source Term Analysis of the Irradiated Graphite in the Core of HTR-10

2017 ◽  
Vol 2017 ◽  
pp. 1-6 ◽  
Author(s):  
Xuegang Liu ◽  
Xin Huang ◽  
Feng Xie ◽  
Fuming Jia ◽  
Xiaogui Feng ◽  
...  
Keyword(s):  
High Temperature ◽  
Source Term ◽  
Pressurized Water Reactor ◽  
Sample Collection ◽  
Analytical Methodology ◽  
Pressurized Water ◽  
The Core ◽  
Irradiated Graphite ◽  
Term Analysis ◽  
High Temperature Gas

The high temperature gas-cooled reactor (HTGR) has potential utilization due to its featured characteristics such as inherent safety and wide diversity of utilization. One distinct difference between HTGR and traditional pressurized water reactor (PWR) is the large inventory of graphite in the core acting as reflector, moderator, or structure materials. Some radionuclides will be generated in graphite during the period of irradiation, which play significant roles in reactor safety, environmental release, waste disposal, and so forth. Based on the actual operation of the 10 MW pebble bed high temperature gas-cooled reactor (HTR-10) in Tsinghua University, China, an experimental study on source term analysis of the irradiated graphite has been done. An irradiated graphite sphere was randomly collected from the core of HTR-10 as sample in this study. This paper focuses on the analytical procedure and the establishment of the analytical methodology, including the sample collection, graphite sample preparation, and analytical parameters. The results reveal that the Co-60, Cs-137, Eu-152, and Eu-154 are the major γ contributors, while H-3 and C-14 are the dominating β emitting nuclides in postirradiation graphite material of HTR-10. The distribution profiles of the above four nuclides are also presented.

High Temperature Gas Loop and Experiments of Finned Fuel-Elements

1966 ◽  
Vol 9 (33) ◽  
pp. 166-174
Author(s):  
Yoshizo OKAMOTO ◽  
Shinichi NEGOYA
Keyword(s):  
High Temperature ◽  
Fuel Elements ◽  
Gas Loop ◽  
High Temperature Gas
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