Abstract
Rapid thermal elevation in boiling water reactor (BWR) is an important factor for nuclear safety and there is a need to develop an analysis code for the transient phenomenon and its validation process. To evaluate the thermal property of transient boiling and its uncertainty, corroborative experimental information is crucial. In particular, the lateral propagation behavior of a vapor bubble (void) in the cross-sectional direction of fuel assembly has yet to be determined. This study evaluates the void propagation behavior in a 5 × 5 rod bundle with cross-sectional heat distribution that causes only the 3 × 3 rod bundle to generate heat; assuming rapid heating under atmospheric pressure. In this paper, using the maximum heat output applied to the nine heated rods as a parameter, from the visualization of the void behavior and the measurement of the local void fraction, the heat output conditions under circumstances where lateral propagation of voids occurs and where voids are only localized in the heated region are summarized. We quantified the time difference initially detected and the time-averaged void fraction according to the lateral propagation level.
| Original language | English |
|---|---|
| Pages (from-to) | 447-456 |
| Number of pages | 10 |
| Journal | Nuclear Engineering and Design |
| Volume | 340 |
| DOIs | |
| Publication status | Published - 2018 Dec 15 |
| Externally published | Yes |
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Keywords
- 5 × 5 rod bundle
- BWR fuel
- Cross vapor propagation
- Rapid heating
- Transient boiling
- Wire mesh sensor
ASJC Scopus subject areas
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Materials Science(all)
- Safety, Risk, Reliability and Quality
- Waste Management and Disposal
- Mechanical Engineering
Cite this
Transient boiling flow in 5 × 5 rod bundle under non-uniform rapid heating. / Takiguchi, Hiroki; Furuya, Masahiro; Arai, Takahiro; Shirakawa, Kenetsu.
In: Nuclear Engineering and Design, Vol. 340, 15.12.2018, p. 447-456.Research output: Contribution to journal › Article
}
TY - JOUR
T1 - Transient boiling flow in 5 × 5 rod bundle under non-uniform rapid heating
AU - Takiguchi, Hiroki
AU - Furuya, Masahiro
AU - Arai, Takahiro
AU - Shirakawa, Kenetsu
PY - 2018/12/15
Y1 - 2018/12/15
N2 - Rapid thermal elevation in boiling water reactor (BWR) is an important factor for nuclear safety and there is a need to develop an analysis code for the transient phenomenon and its validation process. To evaluate the thermal property of transient boiling and its uncertainty, corroborative experimental information is crucial. In particular, the lateral propagation behavior of a vapor bubble (void) in the cross-sectional direction of fuel assembly has yet to be determined. This study evaluates the void propagation behavior in a 5 × 5 rod bundle with cross-sectional heat distribution that causes only the 3 × 3 rod bundle to generate heat; assuming rapid heating under atmospheric pressure. In this paper, using the maximum heat output applied to the nine heated rods as a parameter, from the visualization of the void behavior and the measurement of the local void fraction, the heat output conditions under circumstances where lateral propagation of voids occurs and where voids are only localized in the heated region are summarized. We quantified the time difference initially detected and the time-averaged void fraction according to the lateral propagation level.
AB - Rapid thermal elevation in boiling water reactor (BWR) is an important factor for nuclear safety and there is a need to develop an analysis code for the transient phenomenon and its validation process. To evaluate the thermal property of transient boiling and its uncertainty, corroborative experimental information is crucial. In particular, the lateral propagation behavior of a vapor bubble (void) in the cross-sectional direction of fuel assembly has yet to be determined. This study evaluates the void propagation behavior in a 5 × 5 rod bundle with cross-sectional heat distribution that causes only the 3 × 3 rod bundle to generate heat; assuming rapid heating under atmospheric pressure. In this paper, using the maximum heat output applied to the nine heated rods as a parameter, from the visualization of the void behavior and the measurement of the local void fraction, the heat output conditions under circumstances where lateral propagation of voids occurs and where voids are only localized in the heated region are summarized. We quantified the time difference initially detected and the time-averaged void fraction according to the lateral propagation level.
KW - 5 × 5 rod bundle
KW - BWR fuel
KW - Cross vapor propagation
KW - Rapid heating
KW - Transient boiling
KW - Wire mesh sensor
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U2 - 10.1016/j.nucengdes.2018.10.018
DO - 10.1016/j.nucengdes.2018.10.018
M3 - Article
VL - 340
SP - 447
EP - 456
JO - Nuclear Engineering and Design
JF - Nuclear Engineering and Design
SN - 0029-5493
ER -