Analysis of fluid-structure interaction (FSI) sodium leakage incident at prototype fast breeder reactor Monju by ANSYS
- 1. Institute for Nuclear Science and Technology, Vietnam Atomic Energy Institute, Hanoi (Viet Nam)
Description
INSCSP-R7 Standard Problem based on ENTEK BM Test Facility is investigated by RELAP5 code for prediction of averaged cross-section void fraction in vertical boiling channel of 7 m height. This standard problem also gives a challenge in application of CFD code such as ANSYS CFX to predict void fraction along the channel mentioned above due to: (a) only ten measured averaged cross-section void fraction given along the channel of 7 meters and (b) CFD simulation of boiling flow is mainly appropriate with sub cooled boiling. This study presents prediction of averaged cross-section void fraction along the channel of INSCSP-R7 Standard Problem using ANSYS CFX with calibration of parameter in boiling model based on experiment measured results.(author)
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Additional details
Additional titles
- Original title (Vietnamese)
- Phan tich tuong tac chat luu-ket cau (FSI) trong tai nan ro ri natri tai lo phan ung hat nhan Monju bang chuong trinh tinh toan ANSYS
Publishing Information
- Imprint Title
- Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts
- Imprint Pagination
- 266 p.
- Journal Page Range
- 9 p.
- Report number
- INIS-VN--004
Conference
- Title
- 13. Vietnam Conference on Nuclear Science and Technology
- Original Conference Title
- Hoi nghi Khoa hoc va Cong nghe Hat nhan Toan quoc lan thu 13
- Acronym
- VINANST-13
- Dates
- 7-9 Aug 2019
- Place
- Ha Long City, Quang Ninh (Viet Nam)
INIS
- Country of Publication
- Viet Nam
- Country of Input or Organization
- Viet Nam
- INIS RN
- 51079290
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; FLUID-STRUCTURE INTERACTIONS; LEAKS; MONJU REACTOR
- Descriptors DEC
- BREEDER REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; LMFBR TYPE REACTORS; POWER REACTORS; REACTORS; SIMULATION; SODIUM COOLED REACTORS
Optional Information
- Notes
- 7 refs, 10 figs, 1 tab; This record replaces 50071475 Imprint:Conference program and paper abstracts only