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Journal Articles

Prediction of heater surface temperature change at subcooled flow boiling DNB

Liu, W.; Podowski, M. Z.*

Nihon Kikai Gakkai Netsu Kogaku Konfarensu 2015 Koen Rombunshu (CD-ROM), 2 Pages, 2015/10

This paper gives prediction to the transient heat transfer at Departure of Nucleate Boiling (DNB) point for subcooled flow boiling. The prediction is carried out by solving the heat conduction equations in cylindrical coordinates with convective boundary condition, which changes with the change of the heat transfer mode on the heated surface. DNB is assumed to happen at the complete dryout of liquid sublayer trapped between the heated wall and an elongated vapor clot, during the passing time of the vapor clot. Important parameters including initial thickness of the liquid sublayer, vapor clot length, vapor clot velocity and void fraction etc., are calculated from the Liu - Nariai model. The initial heater surface temperature is derived from the Jens-Lottes correlation. The transient changes of liquid sublayer thickness, surface temperature at DNB are reported. No obvious temperature jumping is observed at DNB. To predict temperate excursion at Critical Heat Flux (CHF), more simulations to the transient boiling and film boiling processes are needed.

Journal Articles

Spectroscopic diagnostics for ITER

Sugie, Tatsuo; Costley, A. E.*; Malaquias, A.*; Walker, C.*

Purazuma, Kaku Yugo Gakkai-Shi, 79(10), p.1051 - 1061, 2003/10

The main regions - the core, the edge, the scrape-off layer, and the divertor - will be probed by an extensive array of spectroscopic instrumentation covering the visible to X-ray wavelength range. Plasma parameters will be determined including impurity species/density/input-flux, ion temperature, He density, fueling ratio, plasma rotation, effective ionic charge and safety factor q. The measurements will be used for plasma control and in studies to understand and improve the performance of ITER. A diagnostic neutral beam (~100 keV) will be installed for Charge Exchange Recombination Spectroscopy. Motional Stark Effect measurements (for q profile) will be made using the heating beam (1 MeV). Diagnostic components, such as mirrors, windows, and optical fibers etc, mounted close to the plasma will experience higher levels of radiation due to neutron, gamma ray and particle irradiations than in present devices. Potentially their performance characteristics can be degraded and so the materials of the components have to be carefully selected and mitigating methods adopted where possible.

Journal Articles

NSRR tests under simulated power oscillation conditions of BWRs

Nakamura, Jinichi; Nakamura, Takehiko; Sasajima, Hideo; Suzuki, Motoe; Uetsuka, Hiroshi

HPR-359, Vol.2, p.34_1 - 34_16, 2002/09

In BWR, power oscillations can occur due to the void fraction fluctuation. To investigate the fuel behavior during power oscillation of BWRs, two types of irradiated fuel rods were tested under simulated power oscillation conditions in the Nuclear Safety Research Reactor(NSRR). One is high burnup BWR fuel (56GWd/t) test, with 4 power oscillation cycles, to clarify the behavior of high burnup fuel. The second one is high enriched fuel(20%,25GWd/t) test, with 7 power cycles, to perform the test under high power conditions. The fuel behavior data, such as cladding elongation, fuel stack elongation, cladding temperature, etc. were obtained in these tests. The DNB did not occur in these tests. The PCI was observed through cladding elongation and fuel stack elongation during the power oscillations, but the residual strain of cladding was very small. Fuel behavior under simulated power oscillations is discussed based on in-pile data and PIE data and is compared with FEMAXI-6 and FRAP-T6 calculation.

JAEA Reports

Steady-state and transient DNB analyses for JAERI passive safety reactor (JPSR) using COBRA-IV-I and RETRAN-02/Mod3 codes

Okubo, Tsutomu; X.Jiang*; Araya, Fumimasa; Ochiai, Masaaki

JAERI-Research 98-042, 49 Pages, 1998/08

JAERI-Research-98-042.pdf:1.58MB

no abstracts in English

Journal Articles

Recent activities on subchannel analysis at JAERI

Okubo, Tsutomu; Araya, Fumimasa; Iwamura, Takamichi; Kusunoki, Tsuyoshi

Fourth Int. Seminar on Subchannel Analysis (ISSCA-4), p.267 - 286, 1997/00

no abstracts in English

Journal Articles

Transient analysis for design of primary coolant pump adopted to JAERI passive safety reactor JPSR

Araya, Fumimasa; Murao, Yoshio; Iwamura, Takamichi

Journal of Nuclear Science and Technology, 32(10), p.1039 - 1046, 1995/10

 Times Cited Count:3 Percentile:37.28(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Behavior of stainless steel cladding fuel under a fast power transient condition; NSRR SC-1 test results

Katanishi, Shoji; Ishijima, Kiyomi; ; Kikuchi, Teruo;

JAERI-Research 94-039, 54 Pages, 1994/11

JAERI-Research-94-039.pdf:5.2MB

no abstracts in English

JAEA Reports

Thermal-hydraulic conceptual design of the multiple purpose research reactor MEX-15

M.A.Lucatero*; Kaminaga, Masanori

JAERI-M 94-006, 38 Pages, 1994/02

JAERI-M-94-006.pdf:1.27MB

no abstracts in English

Journal Articles

Experimental study on DNB heat flux correlations for JMTR safety analysis

; Kaminaga, Masanori; ; Ando, Hiroei; ; Sudo, Yukio;

ANL/RERTR/TM-18, CONF-9009108, 0, p.241 - 248, 1993/00

no abstracts in English

JAEA Reports

Experimental study on DNB heat flux of plate-type fuel in pressurized condition

; ; Kaminaga, Masanori; Ishitsuka, Etsuo; ; Sudo, Yukio; Saito, Minoru;

JAERI-M 92-097, 61 Pages, 1992/07

JAERI-M-92-097.pdf:2.42MB

no abstracts in English

JAEA Reports

Accident simulation tests for high conversion light water reactor using a high pressure water loop

Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio

JAERI-M 92-050, 46 Pages, 1992/03

JAERI-M-92-050.pdf:1.24MB

no abstracts in English

JAEA Reports

Thermohydrodynamic characteristic analysis on the steady state condition of JMTR LEU fuel core

Ishitsuka, Etsuo; Sato, Takeshi; ; Saito, Minoru;

JAERI-M 92-043, 54 Pages, 1992/03

JAERI-M-92-043.pdf:1.45MB

no abstracts in English

JAEA Reports

Evaluation of mechanistic DNB models using HCLWR CHF data

Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

JAERI-M 92-033, 66 Pages, 1992/03

JAERI-M-92-033.pdf:1.37MB

no abstracts in English

Journal Articles

Application of subchannel code to DNB analysis of HCLWR

Iwamura, Takamichi; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio

Subchannel Analysis in Nuclear Reactors, p.281 - 301, 1992/00

no abstracts in English

Journal Articles

Cooling and failure of water reactor fuel in overpower accidents

Sobajima, Makoto

Dai-28-Kai Nihon Dennetsu Shimpojiumu Koen Rombunshu, p.718 - 720, 1991/05

no abstracts in English

Journal Articles

Evaluation of DNBR under operational and accident conditions for double-flat-core type HCLWR

Iwamura, Takamichi; Okubo, Tsutomu; Murao, Yoshio; *; *

Journal of Nuclear Science and Technology, 28(1), p.45 - 58, 1991/01

no abstracts in English

Journal Articles

Safety criterion for burnout of the plate-type fuel in pressurized conditions

; Kaminaga, Masanori; ; Ando, Hiroei; Sudo, Yukio; Saito, Minoru;

Proc. of the Asian Symp. on Research Reactor, p.1 - 8, 1991/00

no abstracts in English

Journal Articles

Behavior of preirradiated fuels under simulated RIA conditions

Ishijima, Kiyomi; Tanzawa, Sadamitsu; Fuketa, Toyoshi;

Proc. on Safety of Thermal Reactors, p.577 - 583, 1991/00

no abstracts in English

JAEA Reports

Critical heat flux experiments for high conversion light water reactor, 3; Heated length: 0.5$$sim$$1.0m, P/D: 1.126$$sim$$1.2, number of rods: 4$$sim$$7

Iwamura, Takamichi; Okubo, Tsutomu; *; ; Murao, Yoshio

JAERI-M 90-044, 158 Pages, 1990/03

JAERI-M-90-044.pdf:2.81MB

no abstracts in English

JAEA Reports

DNBR analyses under steady-state and accident conditions for a double-flat-core high conversion light water reactor

Iwamura, Takamichi; *; Okubo, Tsutomu; ; Murao, Yoshio

JAERI-M 90-043, 70 Pages, 1990/03

JAERI-M-90-043.pdf:1.77MB

no abstracts in English

39 (Records 1-20 displayed on this page)