Published June 2014 | Version v1
Miscellaneous Open

Design of channel experiment equipment for measuring coolant velocity of innovative research reactor

  • 1. Center for Nuclear Reactor Technology and Safety, National Nuclear Energy Agency, Serpong (Indonesia)

Description

The design of innovative high flux research reactor (RRI) requires high power so that the capability core cooling requires to be improved by designing the faster core coolant velocity near to the critical velocity limit. Hence, the critical coolant velocity as the one of the important parameter of the reactor safety shall be measured by special equipment to the velocity limit that may induce fuel element degradation. The research aims is to calculate theoretically the critical coolant velocity and to design the special experiment equipment namely EXNal for measuring the critical coolant velocity in fuel element subchannel of the RRI. EXNal design considers the critical velocity calculation result of 20.52 m/s to determine the variation of flow rate of 4.5-29.2 m3/h, in which the experiment could simulate the 1-4X standard coolant velocity of RSG-GAS as well as destructive test of RRI's fuel plate. (author)

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Part of:
Proceeding on the scientific meeting and presentation on basic research of nuclear science and technology (book I): physics, reactors

Additional details

Additional titles

Original title (Indonesian)
Desain alat eksperimen kanal (EXNal) untuk mengukur kecepatan pendingin reaktor riset inovatif

Publishing Information

Publisher
Center for Accelerator Science and Technology, National Nuclear Energy Agency
Imprint Place
Yogyakarta (Indonesia)
Imprint Title
Proceeding on the scientific meeting and presentation on basic research of nuclear science and technology (book I): physics, reactors
Imprint Pagination
266 p.
Journal Page Range
p. 36-41
ISSN
0216-3128
Report number
INIS-ID--67

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
10-11 Jun 2014
Place
Yogyakarta (Indonesia)

INIS

Country of Publication
Indonesia
Country of Input or Organization
Indonesia
INIS RN
47082676
Subject category
S22: GENERAL STUDIES OF NUCLEAR REACTORS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
COOLANTS; CRITICAL VELOCITY; DESIGN; EXPERIMENTAL CHANNELS; FLOW RATE; FUEL ELEMENTS; RESEARCH REACTORS; THERMAL HYDRAULICS; VELOCITY
Descriptors DEC
FLUID MECHANICS; HYDRAULICS; MECHANICS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIES; REACTORS; RESEARCH AND TEST REACTORS; VELOCITY

Optional Information

Notes
13 refs.; 3 tabs.; 6 figs. Imprint:Prosiding pertemuan dan presentasi ilmiah penelitian dasar ilmu pengetahuan dan teknologi nuklir (buku I): fisika, reaktor