MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility

Reichenberger, Michael A.; Patel, Vishal K.; Roberts, Jeremy A.; Unruh, Troy C.; Mcgregor, Douglas S.

doi:10.1016/j.anucene.2017.02.017

Title: MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility

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Abstract

Micro-Pocket Fission Detectors (MPFDs) are under development for in-core neutron flux measurements at the Transient REActor Test facility (TREAT) and in other experiments at Idaho National Laboratory (INL). The sensitivity of MPFDs to the energy dependent neutron flux at TREAT has been determined for 0.0300-µm thick active material coatings of 242 Pu, 232 Th, natural uranium, and 93% enriched 235 U. Electrode thickness and active material thicknesses for the expected range of values was determined to have negligible effects on the neutron flux in the immediate vicinity of the experiment. Self-shielding effects in the active material of the MPFD was also confirmed to be negligible. Finally, fission fragment energy deposition was found to be in conformance with previously reported results.

Authors:

^[1]; Patel, Vishal K. ^[2];

^[1]; Unruh, Troy C. ^[2]; Mcgregor, Douglas S. ^[1]

Kansas State Univ., Manhattan, KS (United States)
Idaho National Lab. (INL), Idaho Falls, ID (United States)

Publication Date:: Fri Mar 03 00:00:00 EST 2017

Research Org.:: Idaho National Lab. (INL), Idaho Falls, ID (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)

Sponsoring Org.:: USDOE Office of Nuclear Energy (NE)

OSTI Identifier:: 1344930

Alternate Identifier(s):: OSTI ID: 1415237; OSTI ID: 1471057

Report Number(s):: INL/JOU-17-41084-Rev000
Journal ID: ISSN 0306-4549; TRN: US1700652

Grant/Contract Number:: NE0008305; AC07-05ID14517

Resource Type:: Accepted Manuscript

Journal Name:: Annals of Nuclear Energy (Oxford)

Additional Journal Information:: Journal Name: Annals of Nuclear Energy (Oxford); Journal Volume: 104; Journal ID: ISSN 0306-4549

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; 36 MATERIALS SCIENCE; 46 - INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY; Micro; Pocket; Fission; Detector; Chamber; neutron

Citation Formats


                    Reichenberger, Michael A., Patel, Vishal K., Roberts, Jeremy A., Unruh, Troy C., and Mcgregor, Douglas S. MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility.  United States: N. p., 2017. 
Web.  doi:10.1016/j.anucene.2017.02.017.

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                    Reichenberger, Michael A., Patel, Vishal K., Roberts, Jeremy A., Unruh, Troy C., & Mcgregor, Douglas S. MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility.  United States.  https://doi.org/10.1016/j.anucene.2017.02.017

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                    Reichenberger, Michael A., Patel, Vishal K., Roberts, Jeremy A., Unruh, Troy C., and Mcgregor, Douglas S. Fri .  
"MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility".  United States.  https://doi.org/10.1016/j.anucene.2017.02.017.  https://www.osti.gov/servlets/purl/1344930.

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@article{osti_1344930,

  title        = {MCNP6 simulated performance of Micro-Pocket Fission Detectors (MPFDs) in the Transient REActor Test (TREAT) Facility},

  author       = {Reichenberger, Michael A. and Patel, Vishal K. and Roberts, Jeremy A. and Unruh, Troy C. and Mcgregor, Douglas S.},

  abstractNote = {Micro-Pocket Fission Detectors (MPFDs) are under development for in-core neutron flux measurements at the Transient REActor Test facility (TREAT) and in other experiments at Idaho National Laboratory (INL). The sensitivity of MPFDs to the energy dependent neutron flux at TREAT has been determined for 0.0300-µm thick active material coatings of 242 Pu, 232 Th, natural uranium, and 93% enriched 235 U. Electrode thickness and active material thicknesses for the expected range of values was determined to have negligible effects on the neutron flux in the immediate vicinity of the experiment. Self-shielding effects in the active material of the MPFD was also confirmed to be negligible. Finally, fission fragment energy deposition was found to be in conformance with previously reported results.},

  doi          = {10.1016/j.anucene.2017.02.017},

  journal      = {Annals of Nuclear Energy (Oxford)},

  number       = ,

  volume       = 104,

  place        = {United States},

  year         = {Fri Mar 03 00:00:00 EST 2017},

  month        = {Fri Mar 03 00:00:00 EST 2017}

}

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