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Shi, D.*; Xhonneux, A.*; Ueta, Shohei; Verfondern, K.*; Allelein, H.-J.*
Proceedings of 7th International Topical Meeting on High Temperature Reactor Technology (HTR 2014) (USB Flash Drive), 11 Pages, 2014/10
Demonstration tests were conducted using the High Temperature Engineering Test Reactor (HTTR) in Oarai, Japan, to confirm the safety of HTGR technologies and assure the expected physical phenomena to occur under given conditions. As part of the OECD directed LOFC (loss of forced cooling) project, a series of three tests at the HTTR has been planned with tripping of all gas circulators while deactivating all reactor reactivity control to disallow reactor scram due to abnormal reduction of primary coolant flow rate. The tests fall into anticipated transient without scram (ATWS) with occurrence of reactor recriticality. The paper will describe the Source Term Analysis Code System (STACY) newly developed at the Research Center Jlich and present the results of fission product behavior in the HTTR core under the LOFC test conditions. STACY encompasses the original verified and validated computer models for simulating fission product transport and release. For verification of the modernized and extended version, it was assured that results obtained with the original tools could be reproduced. One of the new features of STACY is its ability to also treat fuel compacts of (full) cylindrical or annular shape and a complete prismatic block reactor core, respectively, supposed sufficient input data be available. In the paper, calculations are based on time-dependent neutronics and fluid dynamics results obtained with the Serpent and MGT models.
Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Verfondern, K.*
Journal of Nuclear Science and Technology, 38(6), p.411 - 419, 2001/06
Times Cited Count:17 Percentile:74.85(Nuclear Science & Technology)no abstracts in English
Verfondern, K.*; Sumita, Junya; Ueta, Shohei; Sawa, Kazuhiro
JAERI-Research 2000-067, 127 Pages, 2001/03
no abstracts in English
Nabielek, H.*; Verfondern, K.*; Tang, C.*; Ueta, Shohei
no journal, ,
Burn-leach is the most sensitive method for the determination of High-Temperature Gas-Cooled Reactor fuel quality. German fuel manufacture was for the operation of the 46 MWth AVR. Improvements in the fuel quality were due to perfected tabling of kernels, particles and overcoated particles and the introduction of automated overcoating. Chinese HTGR first load fuel manufacture around 2000 was for the operation of the 10 MWth HTR-10. An improvement can be observed after the first few production runs. Japanese HTGR first fuel manufacture was for the operation of the 30 MWth HTTR. The particle volume density of 30 % is much higher than the below 10 % of the spherical fuel elements. Nevertheless, very good results in terms of low defect fractions were also achieved. These results establish the quality standard in modern UO Triso fuel.