Development of Steam Separator Performance Analysis Code and Its Validation, (III)
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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.
書誌事項
- タイトル別名
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- Development of Steam Separator Performance Analysis Code and Its Validation, (III). Validation of Code for Carryover.
- Validatiop of Code for Carryover
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説明
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.
収録刊行物
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- Journal of Nuclear Science and Technology(日本原子力学会英文論文誌)
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Journal of Nuclear Science and Technology(日本原子力学会英文論文誌) 31 (8), 782-795, 1994
一般社団法人 日本原子力学会
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詳細情報 詳細情報について
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- CRID
- 1390282679071647232
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- NII論文ID
- 130000825669
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- COI
- 1:CAS:528:DyaK2cXls1Gmu7o%3D
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- ISSN
- 18811248
- 00223131
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- CiNii Articles
- OpenAIRE
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- 抄録ライセンスフラグ
- 使用不可