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JAEA Reports

lnvestigation of thermal-hydraulic issues resulting in the use of various coolants

; Yamaguchi, Akira

JNC TN9400 2000-056, 150 Pages, 2000/05

JNC-TN9400-2000-056.pdf:6.67MB

[Purpose] The work was performed to make clear thermal-hydraulic issues resulting in the use of various coolants for fast reactors. [Method] Plant design features due to a use of working fluid other than sodium and design concepts relating a simplification of safety related systems were investigated. And based on the results, quantitative evaluation was made on the topical themal-hydraulic issues. Then both thermal stratification and striping phenomena were evaluated by the used of thermo-hydraulics computer programs. [Results] (1)Thermal-hydraulic issues Topical thermal-hydraulic issues of gaseous and heavy metal cooled reactors were extracted. (a)Gas cooled reactors : natural circulation,flow-induced vibration, depressurization accident (b)Heavy metal cooled reactors : thermal stratification, flow-induced vibration, sloshing And also the thermal-hydraulic issues relating compact reactor assembly and RVACS were extracted resulting from a simplification of safety related systems. (2)Evaluation of thermal stratification and striping phenomena. The following order of affects for the phenomena was obtained: (a) Thermal stratification: CO$$_{2}$$ $$<$$ Sodium $$<$$ Lead, (b) Thermal Striping: CO$$_{2}$$ $$<$$ Lead $$<$$ Sodium

JAEA Reports

Numerical investigation on thermal striping conditions for a tee junction of LMFBR coolant pipes (IV); Investigation on second-order moments in coolant mixing region

JNC TN9400 2000-008, 323 Pages, 2000/02

JNC-TN9400-2000-008.pdf:25.2MB

This rport presents numerical results on theemal striping characteristics at a tee junction of LMFBR coolant pipe, carried out using a direct numerical simulation code DINUS-3. In the numerical investigations, it was considered a tee junction system consisted of a main pipe (1.33 cm$$^{I.D.}$$) with a 90$$^{circ}$$ elbow and a branch pipe, and four parameters, j.e., (1)diameter ratio $$alpha$$ between both the pipes, (2)flow velocity ratio $$beta$$ between both the pipes, (3)angle $$gamma$$ between both the pipes, and (4)Reynolds number Re. From the numerical investigations, the following characteristics were obtained: (1)According to the decreasing of the diameter ratio, significant area of second-order moments was expanded in the fixed condition of $$beta$$=1.0. (2)Significant second-order moments area was expanded for the increasing of the flow velocity ratio $$beta$$ specified by varying of the main pipe velocity in the case of a $$alpha$$ = 1.0 constant condition. 0n the other hand, the area was expanded for the decreasing of the velocity ratio $$beta$$ defined by varying of the branch pipe velocity in the case of a $$alpha$$ = 3.0 constant condition. (3)Maximum second-order moments values were generated in the case of $$gamma$$ = 180$$^{circ}$$ due to the influence of interactions between main pipe flows and jet flows from the branch pipe. (4)According to the increase of Reynolds number, significant area of second-order moments was expanded due to the activation of turbulence mixing in the main pipe.

JAEA Reports

Development of analytical model for evaluating temperature fluctuation in coolant (XII); Investigation of stationary random temperature fluctuation characteristics in frequency domain

PNC TN9410 98-013, 48 Pages, 1998/03

PNC-TN9410-98-013.pdf:1.51MB

Thermal striping phenomena characterized by stationary random temperature fluctuation are observed in the region immediately above the core exit of liquid-metal-cooled fast breeder reactors (LMFBRs) due to the interactions of cold sodium flowing out of a control rod (C/R) assembly and hot sodium flowing out of adjacent fuel assemblies (F/As). Therefore the in-vessel components located in the core outlet region, such as upper core structure (UCS), flow guide tube, C/R upper guide tube, etc., must be protected against the stationary random thermal process which might induce high-cycle fatigue. In this study, frequency characteristics of stationary random temperature fluctuations were investigated by the use of the time-series data from parallel impinging jet experiments, TIFFSS-I. From the investigations, the following results have been obtained; [Auto-Power Spectral Density Functions] (1)Higher frequency componets were decreased drastically with the close to the test piece surface, due to the presence of filtering effect by the laminar sub-layer and heat tansfer to the surface from coolant. (2)Dependence to the nozzle velocities was observed at the outside and inside positions of the laminar sub-layer region. It was due to the increasing of turbulent intensities with increase of the nozzle velocities. [Coherence Functions] (1)Coherency between outer temperatures of the laminar sub-layer was very small. 0ne of the main reasons is that the outer temperatures of the laminar sub-1ayer were dominated by the stationary random phenomena of turbulence flows. (2)It was confirmed that the coherency between immediate positions of different thermocouples had relatively higher values. [Transfer Functions] (1)The dominant frequency band of the gain was about 3 - 10 Hz for the transfer functions of the outer position to the inner position of the laminar sub-layer, and of the inner position of the laminar sub-layer to the test piece surface. (2)There wasno dependence of ...

JAEA Reports

Numerical investigation on thermal striping conditions for a tee junction of LMFBR coolant pipes (I); Investigation on velocity ratio between the coolant pipes

PNC TN9410 98-007, 93 Pages, 1998/02

PNC-TN9410-98-007.pdf:7.52MB

This report presents numeical results on thermal striping charactelistics at a tee junction of LMFBR coolant pipe, carried out using a direct numerical simulation code DINUS-3. In the numerical investigations, it was considered a tee junction system consisted of a main pipe (1.33 cm$$^{I.D.}$$) with a 90$$^{circ}$$ elbow and a branch pipe having same inner diameter to the main pipe, and five velocity ratio conditions between both the pipes, i,e., (V$$_{main}$$ / V$$_{branch}$$) = 0.25; 0.5; 1.0; 2.0 and 4.0. From the numerical investigations, the following characteristics were obtained: (1)Temperature fluctuations in the downstream region of the tee junction were formulated by lower frequency components (< 7.0Hz) due to the iteractions between main pipe flows and jet flows from the branch pipe, and higher frequency components (> 10.0 Hz) generated by the vortex released frequency from the outer edge of the branch pipe jet flows. (2)On the top plane of the main pipe, peak values of the temperature fluctuation amplitude was decreased with increasing flow velocity in the main pipe, and its position was shifted to downstream direction of the main pipe by the increase of the main pipe flow velocity. (3)On the bottom plane of the main pipe, contrary to (2), peak values of the temperature fluctuation amplitude was increased with increasing flow velocity in the main pipe.

JAEA Reports

None

; ; ; ; Yamaguchi, Akira

PNC TN9410 97-017, 280 Pages, 1997/01

PNC-TN9410-97-017.pdf:8.88MB

None

JAEA Reports

Development of analytical model for evaluating temperature fructuation in coolant(VIII); Development of a Monte Carlo direct simulation code THEMIS

PNC TN9410 94-111, 42 Pages, 1994/04

PNC-TN9410-94-111.pdf:1.55MB

Thermal striping phenomena are characterized by stationaly random temperature fluctuations and observed in the region immediately above the core exit of LMFBRs due to the interactions of cold and hot sodium. To evaluate the phenomena, it is neccessary to consider a time-dependent heat transfer coefficient to structures from fluid, in the same manner as a evaluation of a stationaly temperature fluctuation in fluid. For this purpose, a computer program THEMIS (Time-dependent Heat transfer Evaluation by Monte Carlo Direct Simulation) has been developed for the thermohydraulic analysis based on the Boltzmann equation. A two-dimensional duct flow problem has been solved to check the fundamental performance of the THEMIS code. The main results are as follows: (1)Axial distribution of molecular velocity U has shown good agreement with the solution of the Navier-Stokes equation under the condition of Kn=0.0002. (2)An acceleration on the VP-2600 vector processor is about 12 times as the VP-2600 scalar processor. Future works of the THEMIS code development are (1)investigation of the applicabilities in a non-isothermal fluid system and in a complex geometry system and (2)verification with detailed experimental results.

JAEA Reports

Determination of 1991 interim standard values of design fatigue curve for Mod.9Cr-1Mo (NT) steel

; Kawasaki, Hirotsugu; Aoto, Kazumi; Yoshida, Eiichi; ;

PNC TN9410 92-089, 61 Pages, 1992/03

PNC-TN9410-92-089.pdf:1.74MB

The allowable strain range $$varepsilon$$$$_{t}$$ of Mod.9Cr-1Mo (NT) steel has been substituted by that for 2-1/4Cr-1Mo (NT) steel in last version of material strength standard in 1989. Because of the a small amount of fatigue test data on Mod.9Cr-1Mo (NT) steel, it is difficult to determine the best fit curve and allowable strain range $$varepsilon$$$$_{t}$$ of Mod.9Cr-1Mo (NT) steel can be evaluated conservatively by the values of 2-1/4Cr-1Mo (NT) steel. Low-cycle fatigue tests by various strain rates and the high-cycle fatigue tests were carried out to determine the new best fit fatigue life equation of this material. In this report, the fatigue life equation of Mod.9Cr-1Mo (NT) steel is and the interim new version of allowable strain range is proposed. The obtained results are as follows, (1)In the best fit fatigue life equation of Mod.9Cr-1Mo (NT) steel the effects by both of the temperature and low strain rate should be considerd. As the analytical methods to consider these dependency in the fatigue life equation, the correlation to the fatigue properties of 2-1/4Cr-1Mo (NT) steel is examined. Some data fitting methods based on the fatigue equation for 2-1/4Cr-1Mo (NT) steel are tried and compared. One of these methods could give a good prediction for the fatigue properties of the Mod.9Cr-1Mo (NT) steel up to high cycle range. (2)The interim standard of allowable strain ranges A , B and C (for strain rate of 10$$^{-3}$$, 10$$^{-6}$$ and 10$$^{-8}$$ s $$^{-1}$$) for Mod.9Cr-1Mo (NT) steel could be proposed by the new best fit fatigue life equation. (3)The proposed allowable strain range at 375$$^{circ}$$C was compared to the present design fatiuge curve of low alloy steel of MITI Notice No501, and it was clarified that the fatigue strength of Mod.9Cr-1Mo steel was too higher. The design fatigue curve for Mod.9Cr-1Mo (NT) steel will be revised to higher design value (twice for starin range at l0$$^{6}$$ cycles) than the present design fatigue curve of low alloy steel.

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