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Journal Articles

Estimation of mitigation effects of sodium nanofluid for SGTR accidents in SFR

Ichikawa, Kenta*; Kanda, Hironori; Yoshioka, Naoki*; Ara, Kuniaki; Saito, Junichi; Nagai, Keiichi

Proceedings of 26th International Conference on Nuclear Engineering (ICONE-26) (Internet), 6 Pages, 2018/07

Studies on the suppression of the reactivity of sodium itself have been performed on the basis of the concept of suspended nanoparticles in liquid sodium (sodium nanofluid). According to the experimental and theoretical results of studies for sodium nanofluid, velocity and heat of sodium nanofluid-water reaction are lower than those of the pure sodium-water reaction. The analytical model for the peak temperature of a sodium nanofluid-water reaction jet has been developed in consideration of these suppression effects by the authors. In this paper, the prediction method for mitigation effects for a damage of adjacent tubes in a steam generator tube rupture (SGTR) accidents is arranged by applying this analytical model for the peak temperature of the reaction jet. On the assumption that the sodium nanofluid is used for the secondary coolant of sodium-cooled fast reactor (SFR), mitigation effects under the design-base accident (DBA) condition and the design-extension condition (DEC) of SGTR are estimated by using this method. As a result, there is a possibility to reduce the number of damaged tubes and to suppress the pressure generated by SGTR accidents by using sodium nanofluid in the secondary coolant.

JAEA Reports

Study on coincidence and anti-coincidence $$gamma$$-ray spectrometry for the rapid radioactivity evaluation of solidified products prepared from radioactive wastes

Haraga, Tomoko; Kameo, Yutaka; Hoshi, Akiko; Yonezawa, Chushiro*; Nakashima, Mikio

JAERI-Tech 2005-050, 35 Pages, 2005/09

JAERI-Tech-2005-050.pdf:1.35MB

Non-destructive $$gamma$$-ray spectrometry has been examined as a simple and rapid radioactivity measurement technique for the solidified products prepared by plasma melting for low level radioactive miscellaneous wastes generated from nuclear facilities. The Compton background resulting from the coexisting radionuclides pose a problem in the usual $$gamma$$-ray spectrometry which uses only a Ge detector. In order to reduce the background count and to measure the interested nuclide selectively, the coincidence and the anti-coincidence $$gamma$$-ray spectrometry using the Ge-BGO detector system were examined. As a result of applying the anti-coincidence $$gamma$$-ray spectrometry to a single $$gamma$$-ray emitter $$^{137}$$Cs and the coincidence $$gamma$$-ray spectrometry to multiple $$gamma$$-ray emitter $$^{152}$$Eu under existence of $$^{60}$$Co, the detection limits of $$^{137}$$Cs and $$^{152}$$Eu in the sample, which contained $$^{60}$$Co, were reduced by a factor of about 6 and 1.5, respectively. It was confirmed that the present methods are useful for the $$gamma$$-activity measurement of solidified products.

Journal Articles

Shielding design of ITER pressure suppression system

Yamauchi, Michinori*; Sato, Satoshi; Nishitani, Takeo; Kawasaki, Hiromitsu*

Proceedings of 21st IEEE/NPSS Symposium on Fusion Engineering (SOFE 2005) (CD-ROM), 4 Pages, 2005/09

no abstracts in English

Journal Articles

Containment pressure suppression system with functions of water injection and noncondensable gas confinement

Yonomoto, Taisuke; Okubo, Tsutomu; Iwamura, Takamichi; Ishida, Toshihisa

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 8 Pages, 2003/04

An innovative concept of the pressure suppression system having functions of water injection and non-condensable gas confinement is developed for the next generation light water reactors (LWRs). The use of the system is advantageous for the mitigation of effects of the loss-of-coolant accidents (LOCAs) in (1) keeping the containment pressure as low as for the conventional LWRs, (2) injecting water to the containment for cooling the reactor pressure vessel (RPV) and/or flooding a break, and (3) confining the non-condensable gas in the drywell. The gas confinement function makes the system considerably suitable for reactor designs with passive cooling systems utilizing heat exchangers, such as the steam generator (SG) secondary side cooling system for an integral reactor, and the passive containment cooling system (PCCS), because it avoids adverse effects of non-condensable gas on the heat transfer performance during LOCAs. The usefulness of the developed concept is confirmed in the RELAP5/MOD3 code calculation.

JAEA Reports

ITER cryostat main chamber and vacuum vessel pressure suppression system design

*; Nakahira, Masataka; Takahashi, Hiroyuki*; Tada, Eisuke; *; *

JAERI-Tech 99-026, 158 Pages, 1999/03

JAERI-Tech-99-026.pdf:6.58MB

no abstracts in English

Journal Articles

Surge suppression in a power supply of a neutral beam injector

Watanabe, Kazuhiro; Ito, Takao*; Matsuoka, Mamoru

Purazuma, Kaku Yugo Gakkai-Shi, 69(10), p.1229 - 1241, 1993/10

no abstracts in English

Journal Articles

LOCA steam condensation loads in BWR mark II pressure suppression containment system

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Nucl.Eng.Des., 102, p.225 - 228, 1987/00

 Times Cited Count:5 Percentile:50.76(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The Vent-to-vent desynchronization effects on LOCA steam condensation loads in BWR pressure suppression pool

;

Nucl.Eng.Des., 85, p.141 - 150, 1985/00

 Times Cited Count:6 Percentile:64.6(Nuclear Science & Technology)

no abstracts in English

Journal Articles

The LOCA air-injection loads in BWR mark II pressure suppression containment systems

; ;

Nucl.Eng.Des., 77, p.117 - 129, 1984/00

 Times Cited Count:11 Percentile:73.2(Nuclear Science & Technology)

no abstracts in English

Journal Articles

A Compton-suppression array for $$gamma$$-$$gamma$$ coincidence measurements and its application to in-beam experiments

; ; *; *; *

Proc.Int.Symp.on Nuclear Spectroscopy and Nuclear Interactions, p.8 - 9, 1984/00

no abstracts in English

JAEA Reports

Journal Articles

Analytical method for solving fluid-structure interactions in BWR pressure suppression pool

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Nucl.Eng.Des., 75, p.5 - 11, 1982/00

 Times Cited Count:0 Percentile:0.02(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Chugging desynchronization effects on multivent pressure suppression pool loads

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Transactions of the American Nuclear Society, 41, p.695 - 696, 1982/00

no abstracts in English

JAEA Reports

Full-Scale MarkII CRT Program Data Report No.12 (TEST 1205)

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JAERI-M 9405, 121 Pages, 1981/03

JAERI-M-9405.pdf:3.02MB

no abstracts in English

JAEA Reports

Full-scale MarkII CRT Program Data Report No.11 (TEST 1204)

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JAERI-M 9404, 121 Pages, 1981/03

JAERI-M-9404.pdf:2.99MB

no abstracts in English

JAEA Reports

Full-Scale Mark II CRT Program Data Report No.10 (TEST 1203)

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JAERI-M 9403, 122 Pages, 1981/03

JAERI-M-9403.pdf:2.78MB

no abstracts in English

JAEA Reports

Full-Scale Mark-II CRT Program Data Report,No.8; TEST 1201

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JAERI-M 8887, 132 Pages, 1980/06

JAERI-M-8887.pdf:3.8MB

no abstracts in English

35 (Records 1-20 displayed on this page)