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JAEA Reports

Development of a kinetics analysis code for fuel solution combined with thermal-hydraulics analysis code PHOENICS and analysis of natural-cooling characteristic test of TRACY (Contract research)

Watanabe, Shoichi; Yamane, Yuichi; Miyoshi, Yoshinori

JAERI-Tech 2003-045, 73 Pages, 2003/03

JAERI-Tech-2003-045.pdf:4.96MB

Since exact information is not always acquired in the criticality accident of fuel-solution, parametric survey calculations are required for grasping behaviors of the thermal-hydraulics. On the other hand, the practical methods of the calculation which can reduce the computation time with allowable accuracy will be also required, since the conventional method takes a long calculation time. In order to fulfill the requirement, a three-dimensional nuclear-kinetics analysis code considering thermal-hydraulic based on the multi-region kinetic equations with one-group neutron energy was created by incorporating the thermal-hydraulics analysis code PHOENICS as a subroutine. The computation time of the code was shortened by separating time mesh intervals of the nuclear- and heat-calculations from that of the hydraulics calculation, and by regulating automatically the time mesh intervals in proportion to power change rate. A series of analysis were performed for the natural-cooling characteristic test using TRACY in which the power changed slowly for 5 hours after the transient power resulting from the reactivity insertion of a 0.5 dollar. It was found that the code system was able to calculate within the limit of practical time, and acquired the prospect of reproducing the experimental values considerably for the power and temperature change.

Journal Articles

Thermo-hydrodynamic coupling with coolants

Akiba, Masato; R.D.Watson*

Atomic and Plasma-Material Interaction Processes in Controlled Thermonuclear Fusion, p.455 - 480, 1993/00

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-15(Run 75); Investigation of FLECHT-SET coupling test results

Okubo, Tsutomu; Iguchi, Tadashi; ; Murao, Yoshio

JAERI-M 91-227, 89 Pages, 1992/01

JAERI-M-91-227.pdf:1.82MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III test S3-9; Investigation of CCTF coupling test results under an evaluation model condition in PWRs with cold-leg-injection-type ECCS

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-046, 114 Pages, 1990/03

JAERI-M-90-046.pdf:2.26MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III test S3-17; Investigation of thermo-hydrodynamic behavior during reflood phase of LOCA in a PWR with vent valves

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-036, 120 Pages, 1990/03

JAERI-M-90-036.pdf:2.49MB

no abstracts in English

JAEA Reports

Evaluation report on SCTF core-III tests S3-7 and S3-8; Investigation of tie plate water temperature distribution effects on water break-through and core cooling during reflooding in PWRs with combined-injection-type ECCS

Okubo, Tsutomu; Iguchi, Tadashi; Iwamura, Takamichi; ; Onuki, Akira; Abe, Yutaka; *; *; Adachi, Hiromichi; Murao, Yoshio

JAERI-M 90-035, 143 Pages, 1990/03

JAERI-M-90-035.pdf:3.07MB

no abstracts in English

JAEA Reports

Evaluation report on CCTF core-II reflood test C2-AA2(Run 58); Investigation of downcomer injection effects

Okubo, Tsutomu; Iguchi, Tadashi; Sugimoto, Jun; ; Murao, Yoshio

JAERI-M 89-227, 96 Pages, 1990/01

JAERI-M-89-227.pdf:2.12MB

no abstracts in English

JAEA Reports

Evaluation Report on CCTF Core-II Reflood Test C2-4(Run62) Investigation of Reproducibility

; ; *; ; ; Murao, Yoshio

JAERI-M 85-026, 89 Pages, 1985/03

JAERI-M-85-026.pdf:1.82MB

no abstracts in English

JAEA Reports

REFLA-1D/MODE3:A Computer Code for Reflood Thermo-Hydrodynamic Analysis During PWR-LOCA; User's Manual

Murao, Yoshio; ; ; ;

JAERI-M 84-243, 205 Pages, 1985/02

JAERI-M-84-243.pdf:4.22MB

no abstracts in English

JAEA Reports

Design of Slab Core Test Facility(SCTF)in Large Scale Reflood Test Pprogram,Part I :Core-I

; Sudo, Yukio; ; ; ; ; ; ; ; Osakabe, Masahiro; et al.

JAERI-M 83-080, 171 Pages, 1983/06

JAERI-M-83-080.pdf:3.9MB

no abstracts in English

JAEA Reports

12 (Records 1-12 displayed on this page)
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