Void-fraction measurement with high spatial resolution in a 5×5 rod bundle by linear-accelerator-driven X-ray computed tomography over a wide pressure range

Takahiro Arai, Masahiro Furuya, Hiroki Takiguchi, Yoshihisa Nishi, Kenetsu Shirakawa

Research output: Contribution to journalArticle

Abstract

Void fraction (i.e., the volume fraction occupied by gas) is a key parameter for determining the coolability and neutron-moderating performance of a water-cooled nuclear reactor. To develop computational multi-fluid dynamics models for determining the void-fraction distribution, experimental data of comparable quality are required. We have developed a high-energy X-ray computed tomography (CT) system to acquire three-dimensional void-fraction distributions. The CT system comprises a linear-accelerator-driven high-energy X-ray source and a linear detector array. We quantified a boiling two-phase flow in a 5 × 5 heated rod bundle at high pressure, simulating a fuel-rod bundle in a boiling water reactor (BWR). Because the axial travel of the CT system is 4 m and includes the entire BWR fuel-rod bundle, we optimized the CT imaging conditions and reconstruction method for rod-bundle visualization to reduce uncertainties due to density fluctuations in the boiling flow and imaging artifacts. We conducted a boiling experiment at a low flow rate and low thermal power and acquired three-dimensional distributions of the void fraction over a wide pressure range of 0.1–7.2 MPa. The experiment provided three-dimensional void-fraction distributions with high spatial resolution, especially in subchannel regions surrounded by rods, and the results are suitable for validating three-dimensional thermal-hydraulic analysis codes.

Original languageEnglish
Article number101614
JournalFlow Measurement and Instrumentation
Volume69
DOIs
Publication statusPublished - 2019 Oct 1

Fingerprint

Void Fraction
X-ray Tomography
Linear accelerators
Void fraction
Computed Tomography
linear accelerators
Accelerator
Spatial Resolution
bundles
Tomography
voids
Bundle
rods
High Resolution
tomography
spatial resolution
X rays
boiling water reactors
boiling
high resolution

ASJC Scopus subject areas

  • Modelling and Simulation
  • Instrumentation
  • Computer Science Applications
  • Electrical and Electronic Engineering

Cite this

Void-fraction measurement with high spatial resolution in a 5×5 rod bundle by linear-accelerator-driven X-ray computed tomography over a wide pressure range. / Arai, Takahiro; Furuya, Masahiro; Takiguchi, Hiroki; Nishi, Yoshihisa; Shirakawa, Kenetsu.

In: Flow Measurement and Instrumentation, Vol. 69, 101614, 01.10.2019.

Research output: Contribution to journalArticle

@article{47c2fa57121b4756917b900555a1c33e,
title = "Void-fraction measurement with high spatial resolution in a 5×5 rod bundle by linear-accelerator-driven X-ray computed tomography over a wide pressure range",
abstract = "Void fraction (i.e., the volume fraction occupied by gas) is a key parameter for determining the coolability and neutron-moderating performance of a water-cooled nuclear reactor. To develop computational multi-fluid dynamics models for determining the void-fraction distribution, experimental data of comparable quality are required. We have developed a high-energy X-ray computed tomography (CT) system to acquire three-dimensional void-fraction distributions. The CT system comprises a linear-accelerator-driven high-energy X-ray source and a linear detector array. We quantified a boiling two-phase flow in a 5 × 5 heated rod bundle at high pressure, simulating a fuel-rod bundle in a boiling water reactor (BWR). Because the axial travel of the CT system is 4 m and includes the entire BWR fuel-rod bundle, we optimized the CT imaging conditions and reconstruction method for rod-bundle visualization to reduce uncertainties due to density fluctuations in the boiling flow and imaging artifacts. We conducted a boiling experiment at a low flow rate and low thermal power and acquired three-dimensional distributions of the void fraction over a wide pressure range of 0.1–7.2 MPa. The experiment provided three-dimensional void-fraction distributions with high spatial resolution, especially in subchannel regions surrounded by rods, and the results are suitable for validating three-dimensional thermal-hydraulic analysis codes.",
author = "Takahiro Arai and Masahiro Furuya and Hiroki Takiguchi and Yoshihisa Nishi and Kenetsu Shirakawa",
year = "2019",
month = "10",
day = "1",
doi = "10.1016/j.flowmeasinst.2019.101614",
language = "English",
volume = "69",
journal = "Flow Measurement and Instrumentation",
issn = "0955-5986",
publisher = "Elsevier BV",

}

TY - JOUR

T1 - Void-fraction measurement with high spatial resolution in a 5×5 rod bundle by linear-accelerator-driven X-ray computed tomography over a wide pressure range

AU - Arai, Takahiro

AU - Furuya, Masahiro

AU - Takiguchi, Hiroki

AU - Nishi, Yoshihisa

AU - Shirakawa, Kenetsu

PY - 2019/10/1

Y1 - 2019/10/1

N2 - Void fraction (i.e., the volume fraction occupied by gas) is a key parameter for determining the coolability and neutron-moderating performance of a water-cooled nuclear reactor. To develop computational multi-fluid dynamics models for determining the void-fraction distribution, experimental data of comparable quality are required. We have developed a high-energy X-ray computed tomography (CT) system to acquire three-dimensional void-fraction distributions. The CT system comprises a linear-accelerator-driven high-energy X-ray source and a linear detector array. We quantified a boiling two-phase flow in a 5 × 5 heated rod bundle at high pressure, simulating a fuel-rod bundle in a boiling water reactor (BWR). Because the axial travel of the CT system is 4 m and includes the entire BWR fuel-rod bundle, we optimized the CT imaging conditions and reconstruction method for rod-bundle visualization to reduce uncertainties due to density fluctuations in the boiling flow and imaging artifacts. We conducted a boiling experiment at a low flow rate and low thermal power and acquired three-dimensional distributions of the void fraction over a wide pressure range of 0.1–7.2 MPa. The experiment provided three-dimensional void-fraction distributions with high spatial resolution, especially in subchannel regions surrounded by rods, and the results are suitable for validating three-dimensional thermal-hydraulic analysis codes.

AB - Void fraction (i.e., the volume fraction occupied by gas) is a key parameter for determining the coolability and neutron-moderating performance of a water-cooled nuclear reactor. To develop computational multi-fluid dynamics models for determining the void-fraction distribution, experimental data of comparable quality are required. We have developed a high-energy X-ray computed tomography (CT) system to acquire three-dimensional void-fraction distributions. The CT system comprises a linear-accelerator-driven high-energy X-ray source and a linear detector array. We quantified a boiling two-phase flow in a 5 × 5 heated rod bundle at high pressure, simulating a fuel-rod bundle in a boiling water reactor (BWR). Because the axial travel of the CT system is 4 m and includes the entire BWR fuel-rod bundle, we optimized the CT imaging conditions and reconstruction method for rod-bundle visualization to reduce uncertainties due to density fluctuations in the boiling flow and imaging artifacts. We conducted a boiling experiment at a low flow rate and low thermal power and acquired three-dimensional distributions of the void fraction over a wide pressure range of 0.1–7.2 MPa. The experiment provided three-dimensional void-fraction distributions with high spatial resolution, especially in subchannel regions surrounded by rods, and the results are suitable for validating three-dimensional thermal-hydraulic analysis codes.

UR - http://www.scopus.com/inward/record.url?scp=85071717777&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=85071717777&partnerID=8YFLogxK

U2 - 10.1016/j.flowmeasinst.2019.101614

DO - 10.1016/j.flowmeasinst.2019.101614

M3 - Article

VL - 69

JO - Flow Measurement and Instrumentation

JF - Flow Measurement and Instrumentation

SN - 0955-5986

M1 - 101614

ER -