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Ueta, Shohei; Emori, Koichi; Tobita, Tsutomu*; Takahashi, Masashi*; Kuroha, Misao; Ishii, Taro*; Sawa, Kazuhiro
JAERI-Research 2003-025, 59 Pages, 2003/11
In the safety design requirements for the High Temperature Engineering Test Reactor (HTTR) fuel, it is determined that "the as-fabricated failure fraction shall be less than 0.2%" and "the additional failure fraction shall be small through the full service period". Therefore the failure fraction should be quantitatively evaluated during the HTTR operation. In order to measure the primary coolant activity, primary coolant radioactivity signals the in safety protection system, the fuel failure detection (FFD) system and the primary coolant sampling system are provided in the HTTR. The fuel and fission product behavior was evaluated based on measured data in the rise-to-power tests (1) to (4). The measured fractional releases are constant at 210 up to 60% of the reactor power, and then increase to 710 at full power operation. The prediction shows good agreement with the measured value. These results showed that the release mechanism varied from recoil to diffusion of the generated fission gas from the contaminated uranium in the fuel compact matrix.
Sawa, Kazuhiro; Tobita, Tsutomu*; Ueta, Shohei; Suzuki, Shuichi*; Sumita, Junya; Sekita, Kenji; Aoki, Kazunori*; Ouchi, Hiroshi
JAERI-Research 2001-002, 33 Pages, 2001/02
no abstracts in English
Iguchi, Tetsuo; Watanabe, Kenichi*; *; Nose, Shoichi; Harano, Hideki;
JNC TY9400 2000-019, 34 Pages, 2000/05
None
Isozaki, Kazunori; ; Ito, Hideaki; ; Chatani, Keiji; ;
PNC TN9520 93-006, 198 Pages, 1992/11
None
Morimoto, Makoto; Okubo, Toshiyuki; ; ; ; ;
PNC TN9410 91-334, 64 Pages, 1991/10
An failed fuel detection and location system (FFDL) using a sipping method is adopted as the FFDL of Joyo. FFDL has not operated since the first falled fuel simulated (FFDL-I) test in April, 1985 because Joyo has not yet experienced any operation with breached fuels. Therefore, the operational test (II) of FFDL was carried out on July 1219, 1991 for a preparation of the FFDL-II test which is scheduled in 1992. Main results from the test are as follows ; (1)The adequacy of the functions and operating procedure of FFDL was reaffirmed and the operating experience was gained. (2)Radioactivity measurement was conducted by FFDL for six subassemblies and their integrity was confirmed.
; ; ; ;
IEEE Transactions on Nuclear Science, NS-32, p.1209 - 1213, 1985/00
no abstracts in English
; ; ; ; ; ; Asami, Tetsuo
JAERI-M 6862, 22 Pages, 1977/01
no abstracts in English
Nabeshima, Kunihiko; Aizawa, Kosuke; Chikazawa, Yoshitaka; Okazaki, Hitoshi*; Hayashi, Masateru*
no journal, ,
FFD-DN (failed fuel detection system by delayed neutron monitoring) method is to measure the delayed neutron flux which is released from failed fuel to sodium coolant when fuel failure occurs. Here, the part of FFD-DN method will be cleared. Then, reactor trip before fuel failure propagation could be performed by new FFD-DN detection form with BC filter and collimator.
Kato, Shinya; Morohashi, Yuko; Muto, Keitaro
no journal, ,
In order to confirm performance of MONJU failed fuel detection and location system (FFDL), confirmation of accuracy for identifying failed fuel will be conducted by using simulated tag gas.
Morohashi, Yuko; Higuchi, Tetsuo*; Ishii, Keisuke*; Kitamura, Akihiro*
no journal, ,
no abstracts in English