Simulation of Pulsed Neutron Source Reactivity Measurements

Conference · Mon Apr 19 00:00:00 EDT 1993

OSTI ID:6809227

Difilippo, F. C. ^[1]; Caro, M. ^[2]; Williams, T. ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
2. Paul Scherrer Inst. (PSI), Villigen (Switzerland)

A model has been developed to simulate pulsed neutron source experiments which combines a Green's function approach with the statistical samplings of the generation of neutrons by the source and the detection of them by the detector. The response pulse, measured by a multiscaler, is thus simulated allowing confirmation of experimental procedures and analysis of data for measuring the subcriticality of nuclear reactors. The results were applied to the preparation of experiments currently underway at the PROTEUS facility.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Paul Scherrer Inst. (PSI), Villigen (Switzerland)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6809227
• Report Number(s): CONF-930404-4; ON: DE93006210
• Resource Relation: Conference: International Topical Meeting on Mathematical Methods and Supercomputing in Nuclear Applications (M and C+SNA '93) , Karlsruhe (Germany), 19-23 Apr 1993
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
73 NUCLEAR PHYSICS AND RADIATION PHYSICS
HTGR TYPE REACTORS
REACTIVITY WORTHS
PULSED NEUTRON TECHNIQUES
REACTIVITY
COMPUTERIZED SIMULATION
CRITICALITY
GREEN FUNCTION
NEUTRON DETECTION
NEUTRON SOURCES
DETECTION
FUNCTIONS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
PARTICLE SOURCES
RADIATION DETECTION
RADIATION SOURCES
REACTORS
SIMULATION
Nuclear Criticality Safety Program (NCSP)
Pulsed Neutron Source Experiments
Green's Function Approach
Statistical Samplings
PROTEUS Facility
Control Rod Worths
210300* - Power Reactors
Nonbreeding
Graphite Moderated
220100 - Nuclear Reactor Technology- Theory & Calculation