An experimental study on rewetting phenomena in transient conditions of bwrs

Sakae Muto, Takafumi Anegawa, Shinichi Morooka, Seiichi Yokobori, Yukio Takigawa, Shigeo Ebata, Yuichiro Yoshimoto, Shuzi Suzuki

Research output: Contribution to journalArticle

16 Citations (Scopus)

Abstract

It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.

Original languageEnglish
Pages (from-to)311-321
Number of pages11
JournalNuclear Engineering and Design
Volume120
Issue number2-3
DOIs
Publication statusPublished - 1990 Jun 2
Externally publishedYes

Fingerprint

rewetting
rods
experimental study
boiling
Boiling liquids
supersonic commercial air transport
nucleate boiling
Temperature
Nucleate boiling
design analysis
temperature
hydraulics
bundles
Heat flux
heat flux
Mass transfer
Hydraulics

ASJC Scopus subject areas

  • Energy Engineering and Power Technology
  • Nuclear Energy and Engineering
  • Civil and Structural Engineering
  • Mechanical Engineering
  • Safety, Risk, Reliability and Quality

Cite this

An experimental study on rewetting phenomena in transient conditions of bwrs. / Muto, Sakae; Anegawa, Takafumi; Morooka, Shinichi; Yokobori, Seiichi; Takigawa, Yukio; Ebata, Shigeo; Yoshimoto, Yuichiro; Suzuki, Shuzi.

In: Nuclear Engineering and Design, Vol. 120, No. 2-3, 02.06.1990, p. 311-321.

Research output: Contribution to journalArticle

Muto, S, Anegawa, T, Morooka, S, Yokobori, S, Takigawa, Y, Ebata, S, Yoshimoto, Y & Suzuki, S 1990, 'An experimental study on rewetting phenomena in transient conditions of bwrs', Nuclear Engineering and Design, vol. 120, no. 2-3, pp. 311-321. https://doi.org/10.1016/0029-5493(90)90383-9
Muto, Sakae ; Anegawa, Takafumi ; Morooka, Shinichi ; Yokobori, Seiichi ; Takigawa, Yukio ; Ebata, Shigeo ; Yoshimoto, Yuichiro ; Suzuki, Shuzi. / An experimental study on rewetting phenomena in transient conditions of bwrs. In: Nuclear Engineering and Design. 1990 ; Vol. 120, No. 2-3. pp. 311-321.
@article{0e2d71fb6d0a4358a719297a602619fd,
title = "An experimental study on rewetting phenomena in transient conditions of bwrs",
abstract = "It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.",
author = "Sakae Muto and Takafumi Anegawa and Shinichi Morooka and Seiichi Yokobori and Yukio Takigawa and Shigeo Ebata and Yuichiro Yoshimoto and Shuzi Suzuki",
year = "1990",
month = "6",
day = "2",
doi = "10.1016/0029-5493(90)90383-9",
language = "English",
volume = "120",
pages = "311--321",
journal = "Nuclear Engineering and Design",
issn = "0029-5493",
publisher = "Elsevier BV",
number = "2-3",

}

TY - JOUR

T1 - An experimental study on rewetting phenomena in transient conditions of bwrs

AU - Muto, Sakae

AU - Anegawa, Takafumi

AU - Morooka, Shinichi

AU - Yokobori, Seiichi

AU - Takigawa, Yukio

AU - Ebata, Shigeo

AU - Yoshimoto, Yuichiro

AU - Suzuki, Shuzi

PY - 1990/6/2

Y1 - 1990/6/2

N2 - It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.

AB - It is known that rod temperature rise after boiling transition (BT) is not excursive and that the peak cladding temperature (PCT) is suppressed by rewetting to return to nucleate boiling, even if BT occurs under severe conditions exceeding abnormal operational transients for a BWR. The purpose of this study is to develop and verify the rewetting correlation. The rewetting correlation was developed based on single rod data, as a function of quality, mass flux, pressure and heat flux. The transient thermal-hydraulic code used in the BWR design analysis (SCAT) with this rewetting correlation was compared with transient rod temperature result after the occurence of BT obtianed by the 8×8 and 4×4 rod bundle. It is concluded that the transient code with the developed rewetting correlation predicts the PCT conservatively, and the rewetting time well.

UR - http://www.scopus.com/inward/record.url?scp=0000442940&partnerID=8YFLogxK

UR - http://www.scopus.com/inward/citedby.url?scp=0000442940&partnerID=8YFLogxK

U2 - 10.1016/0029-5493(90)90383-9

DO - 10.1016/0029-5493(90)90383-9

M3 - Article

AN - SCOPUS:0000442940

VL - 120

SP - 311

EP - 321

JO - Nuclear Engineering and Design

JF - Nuclear Engineering and Design

SN - 0029-5493

IS - 2-3

ER -