Published August 2019 | Version v1
Miscellaneous Open

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)

Files

51079290.pdf

Files (1.1 MB)

Name Size Download all
md5:852786aae4af792ee9825ea9c3eff6ce
1.1 MB Preview Download
Part of:
Vietnam Conference on Nuclear Science and Technology VINANST-13. Agenda and Abstracts

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