Published June 1996 | Version v1
Miscellaneous

Thermal-Hydraulic Experiment To Test The Stable Operation Of A PIUS Type Reactor

  • 1. Nuclear Technology Assessment Centre, National Atomic Energy Agency, Jakarta, Indonesia (Indonesia)
  • 2. Nagoya University, Nagoya, Japan (Japan)
  • 3. Japan Atomic Energy Research Institute, Japan (Japan)

Description

An advanced type of reaktor concept as the Process Inherent Ultimate Safety (PIUS) reactor was based on intrinsically passive safety considerations. The stable operation of a PIUS type reactor is based on the automation of circulation pump speed. An automatic circulation pump speed control system by using a measurement of the temperature distribution in the lower density lock is proposed the PIUS-type reactor. In principle this control system maintains the fluid temperature at the axial center of the lower density lock at average of the fluid temperatures below and above the lower density lock. This control system will prevent the poison water from penetrating into the core during normal operation. The effectiveness of this control system was successfully confirmed by a series of experiments using atmospheric pressure thermal-hydraulic test loop which simulated the PIUS principle. The experiments such as: start-up and power ramping tests for normal operation simulation and loss of feedwater test for an accident condition simulation, carried out in JAERI

Part of:
Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book I. Physics, Reactor Physics and Nuclear Instrumentation

Additional details

Additional titles

Original title (Indonesian)
Eksperimen Thermo-Hidrolika Untuk Pengujian Operasi Stabil Reaktor Tipe Pius

Publishing Information

Publisher
Yogyakarta Nuclear Research Centre, National Atomic Energy Agency, Yogyakarta
Imprint Place
Yogyakarta (Indonesia)
Imprint Title
Proceeding of the Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology: Book I. Physics, Reactor Physics and Nuclear Instrumentation
Imprint Pagination
280 p.
Series
Prosiding Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir: Buku I. Fisika, Fisika Reaktor, dan Instrumentasi Nuklir
Journal Page Range
p. 95-100
ISSN
0216-3128
Report number
INIS-ID--012

Conference

Title
Scientific Meeting and Presentation on Basic Research of Nuclear Science and Technology
Original Conference Title
Pertemuan dan Presentasi Ilmiah Penelitian Dasar Ilmu Pengetahuan dan Teknologi Nuklir
Dates
25-27 Apr 1995
Place
Yogyakarta (Indonesia)

INIS

Country of Publication
Indonesia
Country of Input or Organization
Indonesia
INIS RN
33001740
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
CONTROL SYSTEMS; DENSITY; HYDRAULIC EQUIPMENT; REACTOR OPERATION; REACTORS; SAFETY ANALYSIS
Descriptors DEC
EQUIPMENT; OPERATION; PHYSICAL PROPERTIES

Optional Information

Notes
author; 5 refs.; 6 figs.