Published 1991 | Version v1
Book

Fundamental study on thermo-hydraulic behaviors of a fuel channel during a severe power transient

  • 1. Tokyo Inst. of Tech. (Japan). Research Lab. of Nuclear Reactor

Description

Thermo-hydraulic behavior during a severe power transient is studied experimentally. A stainless rod of 4mm in diameter and 120mm in length, simulating a fuel rod is transiently heated by Joule heating using discharge of a power condenser charged up to 50KJ. Expansion of transiently developed thermal boundary layer, transient nucleate and film boiling around the heater rod generate a high pressure pulse which is converted to mechanical energy of the fluid. When the power input becomes large enough, the heated rod is melted and dispersed into the liquid. The peak pressure and the mechanical energy due to the transient power input are investigated for various power input and coolant conditions. The main results are; 1. When the heated rod do not melted, there is a combination of power input and subcooling that generates peak pressure and maximum mechanical energy where nucleate boiling is the dominant mechanism through the transient. However, they are suppressed in the high power input region. 2. When the rod melts, the peak pressure and the mechanical energy increase to about 10 times larger than those of the non-melting case. (author)

Additional details

Publishing Information

Publisher
Japan Society of Mechanical Engineers.
Imprint Place
Tokyo (Japan)
Imprint Title
The 1st JSME/ASME joint international conference on nuclear engineering
Imprint Pagination
1273 p.
Journal Page Range
v. 2 p. 227-233.

Conference

Title
1. JSME/ASME joint international conference on nuclear engineering.
Dates
4-7 Nov 1991.
Place
Tokyo (Japan).

Optional Information

Notes
Imprint:Composed of two volumes.