Published 1990 | Version v1
Journal article Metadata-only

On-line thermal power estimation for control and protection of the advanced neutron source reactor

Creators

  • 1. Univ. of Tennessee, Knoxville (United States)
  • 2. Oak Ridge National Lab., TN (United States)

Description

This paper presents an evaluation of several techniques to provide on-line estimation of the thermal power for the advanced neutron source (ANS) reactor. This estimate will be used to convert neutron flux sensor measurements to power units before they are fed into the control and plant protection system. The approach proposed for the ANS thermal power monitor is based on the one used successfully at the High-Flux Isotope Reactor (HFIR), but with modifications to improve its time response and accuracy. The ANS reactor is designed primarily to serve as a source of thermal and very low energy neutrons for scattering experiments

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
62
Journal Page Range
p. 564-565.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
American Nuclear Society (ANS) winter meeting.
Dates
11-16 Nov 1990.
Place
Washington, DC (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
24039010
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONTROL ELEMENTS; DESIGN; EFFICIENCY; HEAVY WATER; NEUTRON SOURCES; PLANNING; POSITIONING; POWER DENSITY; REACTOR CONTROL SYSTEMS; REACTOR MONITORING SYSTEMS; REACTOR PROTECTION SYSTEMS; RESEARCH AND TEST REACTORS; THERMAL NEUTRONS; TRANSIENTS
Descriptors DEC
BARYONS; CONTROL SYSTEMS; ELEMENTARY PARTICLES; ENGINEERED SAFETY SYSTEMS; FERMIONS; HADRONS; HYDROGEN COMPOUNDS; NEUTRONS; NUCLEONS; OXYGEN COMPOUNDS; PARTICLE SOURCES; RADIATION SOURCES; REACTOR COMPONENTS; REACTORS; WATER

Optional Information

Secondary number(s)
CONF-901101--.