Development of Subchannel Void Sensor for Wide Pressure and Temperature Ranges and Its Application to Boiling Flow Dynamics in a Heated Rod Bundle
Author:
Affiliation:
1. Central Research Institute of Electric Power Industry, 2-6-1, Nagasaka, Yokosuka-shi, Kanagawa 240-0196, Japan
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.1080/00295450.2021.1897733
Reference30 articles.
1. NEPTUN-III Reflooding and Boiloff Experiments with an LWHCR Fuel Bundle Simulator: Experimental Results and Initial Code Assessment Efforts
2. Void fraction under high pressure, low flow conditions in rod bundle geometry
3. Void-fraction distribution under high-pressure boil-off conditions in rod bundle geometry
4. Flow Structure of Subcooled Boiling Water Flow in a Subchannel of 3 × 3 Rod Bundles
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1. Validation of a three-dimensional two-phase code, CUPID, using a rod-bundle boiling test facility, SIRIUS-3D;Annals of Nuclear Energy;2024-12
2. A comprehensive review of numerical and experimental research on the thermal-hydraulics of two-phase flows in vertical rod bundles;International Journal of Heat and Mass Transfer;2024-04
3. Validation of a Three-Dimensional Two-Phase Code, Cupid, Using a Rod-Bundle Boiling Test Facility, Sirius-3d;2024
4. Effect of nonheated rod arrangements on void fraction distribution in a rod bundle in high-pressure boiling flow;Nuclear Engineering and Design;2023-02
5. Spatio-temporal characteristics of void fraction in heated rod bundle under saturated pool boiling due to thermal power oscillation;Nuclear Engineering and Design;2023-02
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