CHF enhancement using spherical porous materials in saturated pool boiling of nanofluid

Shoji Mori; Fumihisa Yokomatsu; Kunito Okuyama

CHF enhancement using spherical porous materials in saturated pool boiling of nanofluid

Shoji Mori, Fumihisa Yokomatsu, Kunito Okuyama

Research output: Contribution to conference › Paper › peer-review

Abstract

One strategy for severe accidents is in-vessel retention (IVR) of corium debris. IVR consists of external cooling of the reactor vessel in order to remove decay heat from the molten core through the lower head of the vessel. However, heat removal is limited by the occurrence of the critical heat flux condition (CHF) at the outer surface of the reactor vessel. Therefore we proposed the CHF enhancement technique in a saturated pool boiling by attachment of a honeycomb porous plate (HPP) on the heated surface. However, the reactor vessel to install HPP has curvature, so the key succeeding in IVR depends on how to place the HPP on the surface of reactor vessel with curvature. Accordingly, we propose the way using porous cellulose beads and nanofluid. As a result, the CHF is shown to be enhanced double compared with that of a plain surface of distilled water.

Original language	English
Publication status	Published - 2017
Externally published	Yes
Event	17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 - Xi'an, Shaanxi, China Duration: Sept 3 2017 → Sept 8 2017

Other

Other	17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017
Country/Territory	China
City	Xi'an, Shaanxi
Period	9/3/17 → 9/8/17

All Science Journal Classification (ASJC) codes

Nuclear Energy and Engineering
Instrumentation

Cite this

@conference{ecdbd2a3b2334a0195f14f12afcb3edb,

title = "CHF enhancement using spherical porous materials in saturated pool boiling of nanofluid",

abstract = "One strategy for severe accidents is in-vessel retention (IVR) of corium debris. IVR consists of external cooling of the reactor vessel in order to remove decay heat from the molten core through the lower head of the vessel. However, heat removal is limited by the occurrence of the critical heat flux condition (CHF) at the outer surface of the reactor vessel. Therefore we proposed the CHF enhancement technique in a saturated pool boiling by attachment of a honeycomb porous plate (HPP) on the heated surface. However, the reactor vessel to install HPP has curvature, so the key succeeding in IVR depends on how to place the HPP on the surface of reactor vessel with curvature. Accordingly, we propose the way using porous cellulose beads and nanofluid. As a result, the CHF is shown to be enhanced double compared with that of a plain surface of distilled water.",

author = "Shoji Mori and Fumihisa Yokomatsu and Kunito Okuyama",

note = "Funding Information: A part of this study is the result of “Establishment of In-Vessel Retention for a next generation PWR by heater surface modification” carried out under the Initiatives for Atomic Energy Basic and Generic Strategic Research by the Ministry of Education, Culture, Sports, Science and Technology of Japan Publisher Copyright: {\textcopyright} 2016 Association for Computing Machinery Inc. All Rights Reserved.; 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017 ; Conference date: 03-09-2017 Through 08-09-2017",

year = "2017",

language = "English",

}

TY - CONF

T1 - CHF enhancement using spherical porous materials in saturated pool boiling of nanofluid

AU - Mori, Shoji

AU - Yokomatsu, Fumihisa

AU - Okuyama, Kunito

N1 - Funding Information: A part of this study is the result of “Establishment of In-Vessel Retention for a next generation PWR by heater surface modification” carried out under the Initiatives for Atomic Energy Basic and Generic Strategic Research by the Ministry of Education, Culture, Sports, Science and Technology of Japan Publisher Copyright: © 2016 Association for Computing Machinery Inc. All Rights Reserved.

PY - 2017

Y1 - 2017

N2 - One strategy for severe accidents is in-vessel retention (IVR) of corium debris. IVR consists of external cooling of the reactor vessel in order to remove decay heat from the molten core through the lower head of the vessel. However, heat removal is limited by the occurrence of the critical heat flux condition (CHF) at the outer surface of the reactor vessel. Therefore we proposed the CHF enhancement technique in a saturated pool boiling by attachment of a honeycomb porous plate (HPP) on the heated surface. However, the reactor vessel to install HPP has curvature, so the key succeeding in IVR depends on how to place the HPP on the surface of reactor vessel with curvature. Accordingly, we propose the way using porous cellulose beads and nanofluid. As a result, the CHF is shown to be enhanced double compared with that of a plain surface of distilled water.

AB - One strategy for severe accidents is in-vessel retention (IVR) of corium debris. IVR consists of external cooling of the reactor vessel in order to remove decay heat from the molten core through the lower head of the vessel. However, heat removal is limited by the occurrence of the critical heat flux condition (CHF) at the outer surface of the reactor vessel. Therefore we proposed the CHF enhancement technique in a saturated pool boiling by attachment of a honeycomb porous plate (HPP) on the heated surface. However, the reactor vessel to install HPP has curvature, so the key succeeding in IVR depends on how to place the HPP on the surface of reactor vessel with curvature. Accordingly, we propose the way using porous cellulose beads and nanofluid. As a result, the CHF is shown to be enhanced double compared with that of a plain surface of distilled water.

UR - http://www.scopus.com/inward/record.url?scp=85052522558&partnerID=8YFLogxK

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M3 - Paper

AN - SCOPUS:85052522558

T2 - 17th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2017

Y2 - 3 September 2017 through 8 September 2017

ER -

CHF enhancement using spherical porous materials in saturated pool boiling of nanofluid

Abstract

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All Science Journal Classification (ASJC) codes

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