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)
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