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Development of Steam Separator Performance Analysis Code and Its Validation, (III). Validation of Code for Carryover.
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- MOCHIZUKI Hiroyasu
- O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
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- HIRAO Yasuhiko
- O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
Bibliographic Information
- Other Title
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- Development of Steam Separator Performance Analysis Code and Its Validation, (III)
- Validatiop of Code for Carryover
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Description
The purpose of the present study is to develop computer program models in the separator to analyze the behavior of droplets (carryover) which are ejected from the separator on the basis of physical understanding of phenomena. Firstly, the behavior of steam, liquid film, liquid droplets, and void in the separator are calculated using basic conservation equations coupled with empirical correlations derived from the mock-up test. The behavior of droplets, droplets ejected from the separator are analyzed by the following method. Steam velocity outside the separator was calculated with the versatile 3-dimensional flow analysis code in advance, and the trajectory of each liquid droplet was calculated with the Monte Carlo method. <BR>Wetness fraction around the rated condition of the ATR-type separator was calculated with the developed computer program, and compared with the measured data outside the separator. Good agreement was obtained between calculated and measured results.
Journal
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- Journal of Nuclear Science and Technology
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Journal of Nuclear Science and Technology 31 (8), 782-795, 1994
Atomic Energy Society of Japan
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Keywords
Details 詳細情報について
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- CRID
- 1390282679071647232
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- NII Article ID
- 130000825669
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- COI
- 1:CAS:528:DyaK2cXls1Gmu7o%3D
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- ISSN
- 18811248
- 00223131
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- Text Lang
- en
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- Data Source
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- JaLC
- Crossref
- CiNii Articles
- OpenAIRE
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- Abstract License Flag
- Disallowed