- 【Updated on May 12, 2025】 Integration of CiNii Dissertations and CiNii Books into CiNii Research
- Trial version of CiNii Research Knowledge Graph Search feature is available on CiNii Labs
- 【Updated on June 30, 2025】Suspension and deletion of data provided by Nikkei BP
- Regarding the recording of “Research Data” and “Evidence Data”
Development of Steam Separator Performance Analysis Code and Its Validation, (II). Carryover Experiments.
-
- MOCHIZUKI Hiroyasu
- O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
-
- HIRAO Yasuhiko
- O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corp. Mitsubishi Heavy Industries, Ltd.
Bibliographic Information
- Other Title
-
- Carryover Experiments
Search this article
Description
The purpose of the study is to collect data in order to make models that are applicable to calculate carryover droplets that are generated in and flow out of a steam separator. Various effective tests relevant to separation mechanisms in the separator have been conducted with a full-scale steam separator under atmospheric pressure. Separation behaviors for the top of the riser of the separator and for corrugated-separator were clarified and correlated by the experiment. Distinct patterns about the separation at the corrugated-separator, the separation of discharged droplets by gravity, and the separation of droplets by a screen dryer that is used to dry up the steam were also measured with the facility using a full-scale separator in a vessel simulating the flow area of ATR under the high-pressure and high-temperature condition for various water levels. Each separation data were correlated under the condition of maximum steam and liquid flow rates of 7 and 30.5 kg/s, respectively. Liquid droplets containing a small amount of LiOH at several positions were sampled together with steam by iso-kinetic probes, and the amount of carryover was analyzed in PPT range by the chemical analysis of condensed steam. As a result, basic data for separation mechanisms were obtained, and maximum capacity of the separator was estimated.
Journal
-
- Journal of Nuclear Science and Technology
-
Journal of Nuclear Science and Technology 30 (10), 1059-1070, 1993
Atomic Energy Society of Japan
- Tweet
Keywords
Details 詳細情報について
-
- CRID
- 1390282679072018048
-
- NII Article ID
- 130000825917
-
- COI
- 1:CAS:528:DyaK2cXovVyrsg%3D%3D
-
- ISSN
- 18811248
- 00223131
-
- Text Lang
- en
-
- Data Source
-
- JaLC
- Crossref
- CiNii Articles
-
- Abstract License Flag
- Disallowed