TY - JOUR
T1 - High Flux Isotope Reactor Neutron Spectrum Shape Estimation From Activation Experiment Data
AU - Skutnik, Steven E.
AU - Stanford, Austin C.
N1 - Publisher Copyright:
© 1963-2012 IEEE.
PY - 2023/1/1
Y1 - 2023/1/1
N2 - This article provides a comprehensive review of historical irradiation dosimetry available for different locations within the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). This article includes a summary of the available measured activation target data covering a span of over 15 years and 39 experimental campaigns, including 200 individual sample locations evaluated. Using this broad set of data, we reconstruct historic average neutron spectra shapes for HFIR at various locations, including within the flux trap region, beryllium reflectors, and hydraulic tube (HT) regions, at both the 100-and 85-MW operational power. Our findings indicate that the general axial flux distribution shows a relatively small change in transition from 100-to 85-MW operating power, with differences of-6% to +15% for the thermal energy range and around-16% to +8% for the fast range, indicating a sharper drop-off of the thermal neutron flux away from the axial center. Compared with historical dosimetry estimates of the HFIR flux shape, we generally find a moderately broader axial profile shape for thermal neutrons in the interior target regions for the 100-MW samples evaluated but relatively close agreement for the present 85-MW flux shape for both thermal and fast fluxes.
AB - This article provides a comprehensive review of historical irradiation dosimetry available for different locations within the High Flux Isotope Reactor (HFIR) at Oak Ridge National Laboratory (ORNL). This article includes a summary of the available measured activation target data covering a span of over 15 years and 39 experimental campaigns, including 200 individual sample locations evaluated. Using this broad set of data, we reconstruct historic average neutron spectra shapes for HFIR at various locations, including within the flux trap region, beryllium reflectors, and hydraulic tube (HT) regions, at both the 100-and 85-MW operational power. Our findings indicate that the general axial flux distribution shows a relatively small change in transition from 100-to 85-MW operating power, with differences of-6% to +15% for the thermal energy range and around-16% to +8% for the fast range, indicating a sharper drop-off of the thermal neutron flux away from the axial center. Compared with historical dosimetry estimates of the HFIR flux shape, we generally find a moderately broader axial profile shape for thermal neutrons in the interior target regions for the 100-MW samples evaluated but relatively close agreement for the present 85-MW flux shape for both thermal and fast fluxes.
KW - Activation analysis
KW - High Flux Isotope Reactor (HFIR)
KW - neutron flux spectrum adjustment
KW - neutron measurements
UR - http://www.scopus.com/inward/record.url?scp=85144811530&partnerID=8YFLogxK
U2 - 10.1109/TNS.2022.3226870
DO - 10.1109/TNS.2022.3226870
M3 - Article
AN - SCOPUS:85144811530
SN - 0018-9499
VL - 70
SP - 44
EP - 57
JO - IEEE Transactions on Nuclear Science
JF - IEEE Transactions on Nuclear Science
IS - 1
ER -