Published May 2019 | Version v1
Miscellaneous

The friction characteristics and velocity distribution of pulsatile flows in a rod bundle

  • 1. Fundamental Science on Nuclear Safety and Simulation Technology Laboratory, Harbin Engineering University, Harbin (China)
  • 2. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu (China)

Description

The transient fluctuation of flow rate in a nuclear reactor is a common phenomenon in floating reactors and possible accident scenarios, the response for transient flow determined the damage threshold of fuel assemblies. Friction characteristics and velocity distribution of low-frequency pulsatile flows in a rod bundle have been studied. The experiments were conducted under the time-averaged Reynolds number 1000ta<10000, a comparison of pressure drop and velocity between steady flow and pulsatile flow was conducted. The results indicate that: (1) the averaged pressure drop in pulsatile flows is higher than one in the corresponding steady flows; (2) the averaged pressure drop in pulsatile flows is independent on the pulsation period. The velocity distribution of rod bundle in a whole pulsation period was obtained using PIV technique. The discrepancies of the velocity distribution between the steady flow and unsteady flow were analyzed. In pulsatile flows, during the acceleration portion of the period, the velocity in the rod bundle is improved. During the deceleration portion of the period, the lateral velocity in the rod bundle is improved. The results describe pulsatile behaviors in the rod bundle to contribute a better understanding of transient flow characteristics in fuel assemblies. (author)

Part of:
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)

Additional details

Publishing Information

Imprint Title
Proceedings of the 27th international conference on nuclear engineering (ICONE-27)
Imprint Pagination
[4028 p.]
Journal Page Range
5 p.

Conference

Title
27. international conference on nuclear engineering
Acronym
ICONE-27
Dates
19-24 May 2019
Place
Tsukuba, Ibaraki (Japan)

INIS

Country of Publication
Japan
Country of Input or Organization
Japan
INIS RN
51023782
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
FLOW RATE; FLOW VISUALIZATION; FRICTION; FUEL ELEMENT CLUSTERS; NUCLEAR POWER PLANTS; PRESSURE DROP; PULSATIONS; REYNOLDS NUMBER; SHEAR PROPERTIES; THERMAL HYDRAULICS; TRANSIENTS; VELOCITY
Descriptors DEC
DIMENSIONLESS NUMBERS; FLUID MECHANICS; FUEL ASSEMBLIES; HYDRAULICS; MECHANICAL PROPERTIES; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; THERMAL POWER PLANTS

Optional Information

Notes
Available as Internet Data in PDF format, Folder Name: Track16, Paper ID: ICONE27-1514F.pdf; 14 refs., 10 figs.