scholarly journals Measurement and modelling of postirradiation fission product release from HTGR fuel particles under accident conditions

1978 ◽  
Author(s):  
B.F. Myers ◽  
R.E. Morrissey
Keyword(s):  
Fission Product ◽  
Product Release ◽  
Fuel Particles ◽  
Accident Conditions ◽  
Htgr Fuel

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.

Fission Product Release Behavior of Individual Coated Fuel Particles for High-Temperature Gas-Cooled Reactors

2000 ◽  
Vol 131 (1) ◽  
pp. 36-47 ◽  
Author(s):  
Kazuo Minato ◽  
Kazuhiro Sawa ◽  
Toshio Koya ◽  
Takeshi Tomita ◽  
Akiyoshi Ishikawa ◽  
...  
Keyword(s):  
High Temperature ◽  
Fission Product ◽  
Release Behavior ◽  
Product Release ◽  
Fuel Particles ◽  
High Temperature Gas

Fission product release from ZrC-coated fuel particles during post-irradiation heating at 1800 and 2000°C

1997 ◽  
Vol 249 (2-3) ◽  
pp. 142-149 ◽  
Author(s):  
Kazuo Minato ◽  
Toru Ogawa ◽  
Kousaku Fukuda ◽  
Hajime Sekino ◽  
Isamu Kitagawa ◽  
...  
Keyword(s):  
Fission Product ◽  
Post Irradiation ◽  
Product Release ◽  
Fuel Particles
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