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Title: Loop system with gas control of the power production in the MR reactor

Journal Article · · Sov. At. Energy (Engl. Transl.); (United States)
OSTI ID:5983444

An unsolved problem in reactor design is premature fuel-pin failure on account of mechanical interaction between the fuel and the sheath under nonstationary operating conditions. To examine the effects of this interaction on the viability, the authors have built an experimental system with the MR reactor. To provide for varying the power production over wide ranges, gas regulation based on /sup 3/He as neutron absorber is used. A map of core loading in the MR reactor is provided and variation in power in the experimental fuel assembly in accordance with /sup 3/He pressure and control location is shown. A structural diagram shows the reactor apparatus with gas power control in the experimental pin assembly. The relative changes in channel power in relation to neutron absorber pressure in GCU in channel 1-4 are presented. The results are offered on the power variation in the experimental assembly and reactivity as functions of /sup 3/He pressure in the GCU, together with the calculated data.

OSTI ID:
5983444
Journal Information:
Sov. At. Energy (Engl. Transl.); (United States), Vol. 61:1; Other Information: Translated from At. Energ.; 61: No.1, 20-23(Jul 1986)
Country of Publication:
United States
Language:
English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
FUEL PINS
FUEL ELEMENT FAILURE
HELIUM 3
ENERGY ABSORPTION
MR REACTOR
REACTOR CONTROL SYSTEMS
NEUTRON ABSORBERS
MATERIALS TESTING
COMPUTERIZED SIMULATION
REACTOR CORES
POWER DISTRIBUTION
BERYLLIUM
BURNUP
CONTROL ELEMENTS
DELAYED NEUTRONS
EXPERIMENTAL CHANNELS
FUEL ASSEMBLIES
HELIUM 3 TARGET
HYDROGEN 1
IN CORE INSTRUMENTS
IN PILE LOOPS
ISOTOPE SEPARATION
NEUTRON DIFFUSION EQUATION
NEUTRON FLUX
NEUTRON REACTIONS
REACTOR FUELING
REACTOR KINETICS
REACTOR SAFETY
THERMAL NEUTRONS
TRITIUM
ZIRCONIUM
ABSORPTION
ACCIDENTS
ALKALINE EARTH METALS
BARYON REACTIONS
BARYONS
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
CONTROL SYSTEMS
DIFFERENTIAL EQUATIONS
ELEMENTARY PARTICLES
ELEMENTS
EQUATIONS
EVEN-ODD NUCLEI
FERMIONS
FISSION NEUTRONS
FUEL ELEMENTS
HADRON REACTIONS
HADRONS
HELIUM ISOTOPES
HYDROGEN ISOTOPES
ISOTOPES
KINETICS
LIGHT NUCLEI
METALS
NEUTRONS
NUCLEAR REACTIONS
NUCLEI
NUCLEON REACTIONS
NUCLEONS
ODD-EVEN NUCLEI
RADIATION FLUX
RADIOISOTOPES
REACTOR ACCIDENTS
REACTOR CHANNELS
REACTOR COMPONENTS
REACTOR EXPERIMENTAL FACILITIES
REACTOR INSTRUMENTATION
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SEPARATION PROCESSES
SIMULATION
STABLE ISOTOPES
TARGETS
TESTING
TRANSITION ELEMENTS
YEARS LIVING RADIOISOTOPES
220400* - Nuclear Reactor Technology- Control Systems
220900 - Nuclear Reactor Technology- Reactor Safety
220600 - Nuclear Reactor Technology- Research
Test & Experimental Reactors