Published 1994 | Version v1
Book

Small scale thermal-hydraulic experiment for stable operation of a pius-type reactor

  • 1. Nagoya Univ. (Japan). School of Engineering

Description

Thermal-hydraulic experiments using a small-scale atmospheric pressure test loop have been performed for the Process Inherent Ultimate Safety (PIUS)-type reactor to develop the new pump speed feedback control system. Three feedback control systems based on the measurement of flow rate, differential pressure, and fluid temperature distribution in the lower density lock have been proposed and confirmed by a series of experiments. Each of the feedback control systems had been verified in the simulation experiment such as a start-up simulation test. The automatic pump speed control based on the fluid temperature at the lower density lock was quite effective to maintain the stratified interface between primary water and borated pool water for stable operation of the reactor. (author)

Part of:
Emerging nuclear energy systems

Additional details

Publishing Information

Publisher
World Scientific Publishing Co. Pte. Ltd.
Imprint Place
Singapore (Singapore)
Imprint Title
Emerging nuclear energy systems
Imprint Pagination
576 p.
Journal Page Range
p. 287-292.

Conference

Title
7. international conference on emerging nuclear energy systems.
Acronym
ICENES'93
Dates
20-24 Sep 1993.
Place
Chiba (Japan).

INIS

Country of Publication
Singapore
Country of Input or Organization
Japan
INIS RN
26011380
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BENCH-SCALE EXPERIMENTS; CONTROL SYSTEMS; FLOW RATE; MODIFICATIONS; PRESSURE DEPENDENCE; PUMPS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR STABILITY; TEMPERATURE DISTRIBUTION; VELOCITY
Descriptors DEC
COOLING SYSTEMS; EQUIPMENT; REACTOR COMPONENTS; SAFETY; STABILITY

Optional Information