Stochastic Transport Theory Analysis of the ²⁵²Cf Noise Technique

Conference · Sun Jun 02 04:00:00 EDT 1991 · Transactions of the American Nuclear Society

OSTI ID:5777921

Sutton, T. M. ^[1]; Doub, W. B. ^[2]

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1. Knolls Atomic Power Lab., Schenectady, NY (United States)
2. Westinghouse Electric Corp., West Mifflin, PA (United States)

The Mihalczo ²⁵²Cf-Source-Driven Noise Analysis Technique is an experimental method for determining the reactivity of subcritical systems. The technique employs three detectors: detector 1 contains a ²⁵² Cf spontaneous fission source and responds to ²⁵²Cf fissions, and detectors 2 and 3 respond to neutron absorption reactions in their active volumes. The detector signals are used to form the ratio of power spectral densities (PSDs) r(Ω) = (G₁₂*G₁₃)/(G₁₁G₂₃), where the subscripts denote detector number. To determine the reactivity, one must know how it is related to the measured r(Ω). The authors outline a derivation of this relationship. The relationship obtained differs from others that have appeared in the literature. The causes of these differences are discussed.

• Research Organization: Knolls Atomic Power Lab., Schenectady, NY (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• OSTI ID: 5777921
• Report Number(s): CONF-910603--
• Conference Information: Journal Name: Transactions of the American Nuclear Society Journal Volume: 63
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400* -- Nuclear Reactor Technology-- Control Systems
220600 -- Nuclear Reactor Technology-- Research
Test & Experimental Reactors
252Cf Source Driven Noise Analysis Technique
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
ACTINIDE ISOTOPES
ACTINIDE NUCLEI
ALPHA DECAY RADIOISOTOPES
BARYONS
CALIFORNIUM 252
CALIFORNIUM ISOTOPES
DECAY
DELAYED NEUTRONS
Differences Origins
EFFICIENCY
ELEMENTARY PARTICLES
ENERGY SOURCES
EQUATIONS
EVEN-EVEN NUCLEI
EXPERIMENTAL REACTORS
Experimental Method
FERMIONS
FISSION
FISSION NEUTRONS
FOURIER TRANSFORMATION
FUELS
HADRONS
HEAVY NUCLEI
INTEGRAL TRANSFORMATIONS
ISOTOPES
LANGEVIN EQUATION
MATERIALS
MATHEMATICAL MODELS
NEUTRON ABSORBERS
NEUTRONS
NUCLEAR DECAY
NUCLEAR FUELS
NUCLEAR REACTIONS
NUCLEI
NUCLEONS
Noise Analysis Technique
Nuclear Criticality Safety Program (NCSP)
POWER DENSITY
PROBABILITY
Power Spectral Densities
RADIOISOTOPES
REACTIVITY
REACTOR MATERIALS
REACTOR MONITORING SYSTEMS
REACTOR NOISE
REACTORS
RESEARCH AND TEST REACTORS
Reactivity Determination
SCHOTTKY EFFECT
SPONTANEOUS FISSION
SPONTANEOUS FISSION RADIOISOTOPES
SUBCRITICAL ASSEMBLIES
SUBCRITICALITY
Subcritical Reactivity
TRANSFORMATIONS
YEARS LIVING RADIOISOTOPES