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Journal Articles

Evaluation of breach characteristics of fast reactor fuel pins during steady state irradiation

Oka, Hiroshi*; Kaito, Takeji; Ikusawa, Yoshihisa; Otsuka, Satoshi

Nuclear Engineering and Design, 370, p.110894_1 - 110894_8, 2020/12

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

The objective of this study is to evaluate the reliability of a cumulative damage fraction (CDF) analysis for the prediction of fuel pin breach in fast rector using experimentally obtained fuel pin breach data for the first time. Six breached fuel pins were obtained from steady state irradiation in the EBR-II. Post irradiation examinations revealed that FP gas pressure was the main cause of creep damage in cladding, and that the stress contribution from FCMI was negligible. CDFs evaluated for these pins using in-reactor creep rupture equation, taking into account the irradiation history of cladding temperature and hoop stress due to FP gas pressure, were in the range of 0.7 to 1.4 at the occurrence of breach. This shows clearly that fuel pin breach occurs when the CDF approaches 1.0. The results indicate that CDF analysis would be a reliable method for the prediction of fuel pin breach when appropriate material strength and environmental effects are adopted.

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.

Journal Articles

Prediction of fuel performance and fission gas release behavior during normal operation of the High Temperature Engineering Test Reactor by JAERI and FZJ modeling approach

Sawa, Kazuhiro; Ueta, Shohei; Sumita, Junya; Verfondern, K.*

Journal of Nuclear Science and Technology, 38(6), p.411 - 419, 2001/06

 Times Cited Count:12 Percentile:35.66(Nuclear Science & Technology)

no abstracts in English

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

Development of evaluation method of fuel failure fraction during the high temperature engineering test reactor operation

Sawa, Kazuhiro; Yoshimuta, Shigeharu*; Tobita, Tsutomu*;

JAERI-Research 97-036, 23 Pages, 1997/05

JAERI-Research-97-036.pdf:0.72MB

no abstracts in English

JAEA Reports

JAEA Reports

Irradiation performance and integrity of thorium oxide based coated particle fuels at high burnups

Shiratori, Tetsuo; Akabori, Mitsuo; Fukuda, Kosaku; Tsuruta, Harumichi

JAERI-M 90-144, 64 Pages, 1990/09

JAERI-M-90-144.pdf:6.75MB

no abstracts in English

JAEA Reports

Irradiation Experiment of Coated Particle Fuels by Sweep Gas Capsule(Irradiation by 74F-9J Capsule)

; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune; ;

JAERI-M 84-054, 65 Pages, 1984/03

JAERI-M-84-054.pdf:2.84MB

no abstracts in English

JAEA Reports

Irradiation Behaviors of Coated Fuel Particles (V) (Irradiation by JMTR 73F-13A capsule)

; ; ; Minato, Kazuo; Ikawa, Katsuichi; Iwamoto, K.;

JAERI-M 83-232, 67 Pages, 1984/01

JAERI-M-83-232.pdf:6.33MB

no abstracts in English

Journal Articles

Irradiation experiments of VHTR reference fuels by an in-pile gas loop(OGL-1)

; ; ; Minato, Kazuo; ; Ikawa, Katsuichi

Nippon Genshiryoku Gakkai-Shi, 26(1), p.57 - 74, 1984/00

 Times Cited Count:1 Percentile:80.31(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Detection of failed coated particles in HTGR fuels by acid leaching

; Minato, Kazuo; Ikawa, Katsuichi; ;

Journal of Nuclear Science and Technology, 18(11), p.887 - 894, 1982/00

 Times Cited Count:4 Percentile:46.63(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Release behavior of gaseous fission product from coated fuel particles under irradiation

; ; ; Ikawa, Katsuichi; Iwamoto, K.; Yamamoto, Katsumune

Journal of Nuclear Science and Technology, 19(11), p.889 - 902, 1982/00

 Times Cited Count:2 Percentile:66.29(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Irradiation Behaviors of Coated Fuel Particles(IV) (Irradiation by JMTR 73F-12A Capsule)

; ; ; Ikawa, Katsuichi; Iwamoto, K.;

JAERI-M 9644, 50 Pages, 1981/09

JAERI-M-9644.pdf:5.12MB

no abstracts in English

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