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JAEA Reports

An Investigation of fuel and fission product behavior in rise-to-power test of HTTR, 2; Results up to 30 MW operation

Ueta, Shohei; Emori, Koichi; Tobita, Tsutomu*; Takahashi, Masashi*; Kuroha, Misao; Ishii, Taro*; Sawa, Kazuhiro

JAERI-Research 2003-025, 59 Pages, 2003/11

JAERI-Research-2003-025.pdf:2.53MB

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 2$$times$$10$$^{-9}$$ up to 60% of the reactor power, and then increase to 7$$times$$10$$^{-9}$$ 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.

JAEA Reports

An Investigation of fuel and fission product behavior in start-up test of HTTR, 1; Result up to 15MW operation

Sawa, Kazuhiro; Tobita, Tsutomu*; Ueta, Shohei; Suzuki, Shuichi*; Sumita, Junya; Sekita, Kenji; Aoki, Kazunori*; Ouchi, Hiroshi

JAERI-Research 2001-002, 33 Pages, 2001/02

JAERI-Research-2001-002.pdf:1.42MB

no abstracts in English

JAEA Reports

None

Iguchi, Tetsuo; Watanabe, Kenichi*; *; Nose, Shoichi; Harano, Hideki;

JNC TY9400 2000-019, 34 Pages, 2000/05

JNC-TY9400-2000-019.pdf:0.79MB

None

JAEA Reports

None

Isozaki, Kazunori; ; Ito, Hideaki; ; Chatani, Keiji; ;

PNC TN9520 93-006, 198 Pages, 1992/11

PNC-TN9520-93-006.pdf:6.18MB

None

JAEA Reports

Operational test (II) of falled fuel detection and location system (FFDL) of Joyo

Morimoto, Makoto; Okubo, Toshiyuki; ; ; ; ;

PNC TN9410 91-334, 64 Pages, 1991/10

PNC-TN9410-91-334.pdf:1.72MB

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 12$$sim$$19, 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.

Journal Articles

Performance of fuel failure detection system for coated particle fuels

; ; ; ;

IEEE Transactions on Nuclear Science, NS-32, p.1209 - 1213, 1985/00

no abstracts in English

JAEA Reports

Location of Failed Fuel Elements in JRR-2

; ; ; ; ; ; Asami, Tetsuo

JAERI-M 6862, 22 Pages, 1977/01

JAERI-M-6862.pdf:0.84MB

no abstracts in English

Oral presentation

Improvement of JSFR failed fuel detection system by delayed neutron monitoring

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 B$$_{4}$$C filter and collimator.

Oral presentation

Performance confirmation of MONJU failed fuel detection and location system, 3; Performance confirmation of MONJU FFDL using simulant tag gas

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.

Oral presentation

Performance confirmation of MONJU failed fuel detection and location system, 4; Proposal for tagging gas failed fuel detection and location system

Morohashi, Yuko; Higuchi, Tetsuo*; Ishii, Keisuke*; Kitamura, Akihiro*

no journal, , 

no abstracts in English

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