Published October 1987 | Version v1
Journal article Metadata-only

Analysis of rapid transient processes in the polish MP-type research reactor

Creators

  • 1. Institute of Atomic Energy, Swerk, Poland

Description

The pointwise program TOTEM, developed for the purpose of performing safety analysis on the Maryland research reactor, makes it possible to calculate the axial and radial temperature distributions for a fuel assembly at average power and reactivity, taking into account the feedback and the calculated changes in power. The program has been partially verified experimentally. This paper provides further experimental verification for the program by an investigation of the spatial dependence of the neutron flux density and the change in coolant temperature in an operating reactor channel during a rapidly occurring transient

Additional details

Publishing Information

Journal Title
Sov. At. Energy (Engl. Transl.)
Journal Volume
62
Journal Issue
4
Series
Sov. At. Energy (Engl. Transl.).
Journal Page Range
312-315
ISSN
0038-531X
CODEN
SATEA

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
19028891
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
COMPUTERIZED SIMULATION; FEEDBACK; FLUX DENSITY; FUEL ASSEMBLIES; MARYLA REACTOR; NEUTRON FLUX; POWER DISTRIBUTION; PRIMARY COOLANT CIRCUITS; REACTIVITY; REACTOR ACCIDENTS; REACTOR CHANNELS; REACTOR KINETICS; REACTOR SAFETY; REACTOR SAFETY EXPERIMENTS; SENSITIVITY; SYSTEMS ANALYSIS; T CODES; TEMPERATURE DISTRIBUTION; TEMPERATURE GRADIENTS; TRANSIENTS; WATER
Descriptors DEC
ACCIDENTS; COMPUTER CODES; COOLING SYSTEMS; DISTRIBUTION; ENRICHED URANIUM REACTORS; EXPERIMENTAL REACTORS; HYDROGEN COMPOUNDS; KINETICS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POOL TYPE REACTORS; RADIATION FLUX; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; SOLVENTS; SPATIAL DISTRIBUTION; WATER COOLED REACTORS; WATER MODERATED REACTORS; ZERO POWER REACTORS

Optional Information

Notes
Translated from At. Energ.; 62: No. 4, 263-265(Apr 1987).