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JAEA Reports

Analysis of metallic salt granulation preocess, II

Tokuoka, Naochika*; Kobayashi, Mamoru*; Koyama, Takashi*

PNC TJ1636 96-001, 64 Pages, 1996/03

PNC-TJ1636-96-001.pdf:14.63MB

None

JAEA Reports

Sodium fire test at broad ranges of temperatures and oxygen concentrations (1); Effect of leak patterns on ignition temperatures

Kawada, Koji*; ; Hiroi, Hiroshi*; Himeno, Yoshiaki

PNC TN9410 88-004, 44 Pages, 1988/01

PNC-TN9410-88-004.pdf:6.85MB

Since sodium leak and fire researches have been performed at high-temperatures simulating an accident during the rated reactor operation knowledge of sodium leak and fire at low-temperatures which may happen at Ex-vessel Storage Tank or during the partial power operation of the reactor was very li,ited. Therefore, the present test was carried out to clarify the ignition temperatures and the temperature at which aerosol starts to release during sodium spray, column, and pool fires. Sodium spray and column tests were conducted at Sodiu Fire Test Rig (SOFT-1), while sodium pool test was carried out at Sodium Leak Fire and Aerosol Test Rig (SOLFA-1). The following test results were obtained from these tests. (1)Sodium Spray Test. The ignition temperature was 160$$^{circ}$$C depending upon the droplet diameter of sprayed sodium. (2)Sodium Column Test. (a)Sodium main flow did not ignite, while the scattered sodium droplets ignited. (b)The ignition temperature of the main flow rebounded on a pan was 180$$^{circ}$$C. (c)The ignition temperature of deposits on a pan was 160 $$^{circ}$$C. (3)Sodium Pool Test. (a)The ignition temperature of the static pool ranged from 280 to 315$$^{circ}$$C. (b)Temperature at which aerosol starts to release was determined to be 140 to 160$$^{circ}$$C by visual in spection. (c)After extinguished artificially by closing a lid, sodium reignited at temperatures higher than 80 $$^{circ}$$C when the lid was reopend.

JAEA Reports

Basic test on sodium fire protection systems (4); Water simulation test of a leak from IHTS pipe

Himeno, Yoshiaki; *; *

PNC TN9410 86-088, 37 Pages, 1986/08

PNC-TN9410-86-088.pdf:3.3MB

In the safety evaluation of the Monju design basis sodium leak accident, a large leak from an IHTS pipe whose leak hole is equivalent to (1/4)$$cdot$$Dt (where, D is the pipe diameter and t is the pipe wall thickness) is postulated. To investigate the possible occurrence of a spray fire in the event of a sodium leak, a water simulation test has been conducted. Three test sections (straight, elbow, and T pipes) of the full-mockup Monju ITHS pipes with thermal insulation jackets (the jackets consisted of an inner and an outer jackets) were manufactured for this purpose. The test was divided into two parts. One was with the test sections equipped with their inner jacket only and the other with the test sections equipped with both inner and outer jackets. Subjects investigated in the test were (a) leakage flow pattern, (b) fraction of spray flow among a total leak flow, (c) droplet diameters of a spray flow, and (d) pressure drop coefficient across a leak hole and the thermal insulation jackets. From the test results, the following conclusions were drawn. (1)Test sections with the inner jackets only. More than 50% of a leak flow is in the form of a spray. Number mean diameter of the spray droplets determined is several millimeters. (2)Test sections equipped with both inner and outer jackets. A spray formation is almost perfectly suppressed. Since an integrity of the thermal insulation jackets during a leak has already been confirmed, the results indicates that a spray fire does not occur in the event of an real sodium leak. (3)Pressure drop coefficient across a leak hole and thermal insulation jackets Pressure drop coefficient determined is 2.3-2.8. While, the pressure drop coefficient used in the safety evaluation of the Monju sodium leak accident is 1.0. Comparison of these two numbers indicates that the safety margin of the Monju safety evaluation in regard to a sodium leak flow is about 50%. It is also Confirmed that the most part of the pressure ...

JAEA Reports

Calculation code PULCO for purex process in pulsed column

Gonda, Kozo; Matsuda, Teruo*

PNC TN841 82-19, 363 Pages, 1982/03

PNC-TN841-82-19.pdf:8.55MB

no abstracts in English

Oral presentation

Effect of flow obstacle on droplet size distribution in vertical annular air-water flow

Shibamoto, Yasuteru; Yonomoto, Taisuke

no journal, , 

no abstracts in English

Oral presentation

Effects of physical properties of liquid on droplet diameter and distribution in emulsion flow column

Hirayama, Mikiro; Naganawa, Hirochika; Nagano, Tetsushi; Nii, Susumu*

no journal, , 

no abstracts in English

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