28 June 2015 to 2 July 2015
JW Marriott Starr Pass Resort
Etc/GMT-7 timezone

Transient heat transfer from a wire to a forced flow of subcooled liquid hydrogen passing through a vertically-mounted pipe

1 Jul 2015, 09:00
2h
Exhibit Hall (Arizona Ballroom) ()

Exhibit Hall (Arizona Ballroom)

Poster Presentation CEC-12 - Fluid Mechanics, Heat Transfer, and Cryogen Properties C3PoC - Convective Heat Transfer

Speaker

HIDEKI TATSUMOTO (Japan Atomic Energy Agency)

Description

Liquid hydrogen has been used as a fuel for a rocket engine and moderator material for cold neutron source. Recently, it is expected as a coolant for high-Tc superconducting devices because of its excellent cooling properties. The knowledge of transient heat transfer in forced flow of liquid hydrogen is necessary for the cooling design. However, there have been no experimental data on the transient heat transfer in liquid hydrogen as far as we know. In this work, transient heat transfer from a wire inserted into a vertically-mounted pipe to forced flow of subcooled liquid hydrogen with a temperature of 21 K and pressures of 0.4 and 0.7 MPa was measured by exponentially increasing heat input, Q = Q0 exp (t/Τ) where t is time and Τ is period. The Pt-Co wire heater has a diameter of 1.2 mm and length of 60 mm and 120 mm and is inserted into the pipe with a diameter of 8.0 mm, which is made of Fiber reinforced plastic due to thermal insulation. With increase in the heat flux up to the onset of nucleate boiling, surface temperature increases along the curve predicted by Dittus-Boelter correlation for longer period, where it can be almost regarded as steady-state. For shorter period, the heat transfer becomes higher than Dittus-Boelter correlation. In nucleate boiling regime, the heat flux steeply increases up to the transient DNB (departure from nucleate boiling) heat flux, which becomes higher for shorter period. Effect of flow velocity, period and heated length on the transient DNB heat flux was clarified.

Primary author

HIDEKI TATSUMOTO (Japan Atomic Energy Agency)

Co-authors

Dr Hiroaki Kobayashi (JAXA) Masahiro Shiotsu (Kyoto University) Prof. Satoshi Nonaka (JAXA) Prof. Yasuyuki Shirai (Kyoto University) Prof. Yoshifumi Inatani (JAXA) Dr Yoshihiro Naruo (JAXA)

Presentation Materials

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