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 ◽  
...  
2000 ◽  
Vol 279 (2-3) ◽  
pp. 181-188 ◽  
Author(s):  
Kazuo Minato ◽  
Toru Ogawa ◽  
Toshio Koya ◽  
Hajime Sekino ◽  
Takeshi Tomita

Author(s):  
Xiaochuan Zang ◽  
Tao Liu

The emergency action level (EAL) scheme for a modular high temperature gas-cooled reactor (HTR) plant refers to the generic EAL development guidance for pressurized water reactors (PWR) with HTR modification due to its design issues. Based on reactor’s accidents analysis and consequence assessment, EAL scheme of HTR is established through the steps of category and classification. Four emergency classes are set for HTR consisting of U (Emergency Standby), A (Facilities Emergency), S (Site Area Emergency) and G (General Emergency). The Recognition Category of Initiating Condition (IC) and EAL contains A - Abnormal Rad Levels / Radiological Effluent, F - Fission Product Barrier, H - Hazards and Other Conditions Affecting Plant Safety, S - System Malfunction. The methodology for development of EALs for HTR on Fission Product Barrier and System Malfunction has some differences from PWR’s due to differences on operating mode, inherent safety features and system characteristics.


1997 ◽  
Vol 249 (2-3) ◽  
pp. 142-149 ◽  
Author(s):  
Kazuo Minato ◽  
Toru Ogawa ◽  
Kousaku Fukuda ◽  
Hajime Sekino ◽  
Isamu Kitagawa ◽  
...  

2015 ◽  
Author(s):  
◽  
Lukas Michael Carter

High-temperature gas-cooled reactors (HTGRs) are one of the candidates being considered for the replacement of current nuclear reactor designs. Diffusion coefficients for fission products in HTGR graphite are required for estimation of fission product release rates from such reactors. We developed a method for analysis of fission product of fission product surrogate release rates from heated graphite samples. The graphite samples were infused with fission product surrogate material, and material which diffused from the graphite samples was transported via a carbon aerosol laden He jet system to an online inductively coupled plasma mass spectrometer for quantification of the release rate. Diffusion coefficients for cesium in IG-110 and NBG-18 grade nuclear graphites are reported.


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