A new MCNPX PTRAC coincidence capture file capability: a tool for neutron detector design

Conference · Tue Dec 14 00:00:00 EST 2010

OSTI ID:1044157

Evans, Louise G ^[1]; Schear, Melissa A ^[1]; Hendricks, John S ^[1]; Swinhoe, Martyn T ^[1]; Tobin, Stephen J ^[1]; Croft, Stephen ^[1]

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1. Los Alamos National Laboratory

The existing MCNPX{trademark} PTRAC coincidence capture file allows a full list of neutron capture events to be recorded in any simulated detection medium. The originating event history number (e.g. spontaneous fission events), capture time, location and source particle number are tracked and output to file for post-processing. We have developed a new MCNPX PTRAC coincidence capture file capability to aid detector design studies. New features include the ability to track the isotopes that emitted the detected neutrons as well as induced fission chains in mixed samples before detection (both generation number and isotope). Here, the power of this tool is demonstrated using a detector design that has been developed for the non-destructive assay (NDA) of spent nuclear fuel. Individual capture time distributions have been generated for neutrons originating from Curium-244 source spontaneous fission events and induced fission events in fissile isotopes of interest: namely Plutonium-239, Plutonium-241, and Uranium-235. Through this capability, a full picture for the attribution of neutron capture events in the detector can be simulated.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• Sponsoring Organization: USDOE
• DOE Contract Number: AC52-06NA25396
• OSTI ID: 1044157
• Report Number(s): LA-UR-10-08289; LA-UR-10-8289; TRN: US1203347
• Resource Relation: Conference: Waste Management Symposium 2011 ; February 27, 2011 ; Phoenix, AZ
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES
46 INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY
97 MATHEMATICAL METHODS AND COMPUTING
CAPTURE
CURIUM 244
DESIGN
DETECTION
FISSION
NEUTRON DETECTORS
NEUTRON REACTIONS
NEUTRONS
NUCLEAR FUELS
PLUTONIUM 239
PLUTONIUM 241
SPONTANEOUS FISSION
URANIUM 235
WASTE MANAGEMENT