Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

Favalli, Andrea; Vo, D.; Grogan, Brandon R.; Jansson, Peter; Liljenfeldt, Henrik; Mozin, Vladimir; Schwalbach, P.; Sjoland, A.; Tobin, Stephen J.; Trellue, Holly; Vaccaro, S.

doi:10.1016/j.nima.2016.02.072

Title: Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden

Full Record
Other Related Research

Abstract

For the purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project, we hope to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. Moreover, the NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). A purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute ¹³⁷Cs count rate and the ¹⁵⁴Eu/¹³⁷Cs, ¹³⁴Cs/¹³⁷Cs, ¹⁰⁶Ru/¹³⁷Cs, and ¹⁴⁴Ce/¹³⁷Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior overmore »« less

Authors:

Favalli, Andrea ^[1]; Vo, D. ^[1]; Grogan, Brandon R. ^[2]; Jansson, Peter ^[3]; Liljenfeldt, Henrik ^[2]; Mozin, Vladimir ^[4]; Schwalbach, P. ^[5]; Sjoland, A. ^[6]; Tobin, Stephen J. ^[1]; Trellue, Holly ^[1]; Vaccaro, S. ^[5]

Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
Uppsala Univ., Uppsala (Sweden)
Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
European Commission (Luxemburg)
Swedish Nuclear Fuel and Waste Management Co., Stockholm (Sweden)

Publication Date:: Fri Feb 26 00:00:00 EST 2016

Research Org.:: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States); Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)

Sponsoring Org.:: USDOE National Nuclear Security Administration (NNSA)

OSTI Identifier:: 1267063

Alternate Identifier(s):: OSTI ID: 1304714; OSTI ID: 1359636

Report Number(s):: LA-UR-15-29638
Journal ID: ISSN 0168-9002; DN4001030; MDGA517

Grant/Contract Number:: AC05-00OR22725; AC52-06NA25396

Resource Type:: Accepted Manuscript

Journal Name:: Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment

Additional Journal Information:: Journal Volume: 820; Journal ID: ISSN 0168-9002

Publisher:: Elsevier

Country of Publication:: United States

Language:: English

Subject:: 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; passive gamma; initial enrichment; burnup; cooling time; nondestructive assay of spent fuel; Germanium detector; LaBr3 detector; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS

Citation Formats


                    Favalli, Andrea, Vo, D., Grogan, Brandon R., Jansson, Peter, Liljenfeldt, Henrik, Mozin, Vladimir, Schwalbach, P., Sjoland, A., Tobin, Stephen J., Trellue, Holly, and Vaccaro, S. Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden.  United States: N. p., 2016. 
Web.  doi:10.1016/j.nima.2016.02.072.

Copy to clipboard


                    Favalli, Andrea, Vo, D., Grogan, Brandon R., Jansson, Peter, Liljenfeldt, Henrik, Mozin, Vladimir, Schwalbach, P., Sjoland, A., Tobin, Stephen J., Trellue, Holly, & Vaccaro, S. Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden.  United States.  https://doi.org/10.1016/j.nima.2016.02.072

Copy to clipboard


                    Favalli, Andrea, Vo, D., Grogan, Brandon R., Jansson, Peter, Liljenfeldt, Henrik, Mozin, Vladimir, Schwalbach, P., Sjoland, A., Tobin, Stephen J., Trellue, Holly, and Vaccaro, S. Fri .  
"Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden".  United States.  https://doi.org/10.1016/j.nima.2016.02.072.  https://www.osti.gov/servlets/purl/1267063.

Copy to clipboard


                    
@article{osti_1267063,

  title        = {Determining initial enrichment, burnup, and cooling time of pressurized-water reactor spent fuel assemblies by analyzing passive gamma spectra measured at the Clab interim-fuel storage facility in Sweden},

  author       = {Favalli, Andrea and Vo, D. and Grogan, Brandon R. and Jansson, Peter and Liljenfeldt, Henrik and Mozin, Vladimir and Schwalbach, P. and Sjoland, A. and Tobin, Stephen J. and Trellue, Holly and Vaccaro, S.},

  abstractNote = {For the purpose of the Next Generation Safeguards Initiative (NGSI)–Spent Fuel (SF) project, we hope to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. Moreover, the NGSI–SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: (1) verify the initial enrichment, burnup, and cooling time of facility declaration; (2) detect the diversion or replacement of pins; (3) estimate the plutonium mass [which is also a function of the variables in (1)]; (4) estimate the decay heat; and (5) determine the reactivity of spent fuel assemblies. Since August 2013, a set of measurement campaigns has been conducted at the Central Interim Storage Facility for Spent Nuclear Fuel (Clab), in collaboration with Swedish Nuclear Fuel and Waste Management Company (SKB). A purpose of the measurement campaigns was to acquire passive gamma spectra with high-purity germanium and lanthanum bromide scintillation detectors from Pressurized Water Reactor and Boiling Water Reactor spent fuel assemblies. The absolute 137Cs count rate and the 154Eu/137Cs, 134Cs/137Cs, 106Ru/137Cs, and 144Ce/137Cs isotopic ratios were extracted; these values were used to construct corresponding model functions (which describe each measured quantity’s behavior over various combinations of burnup, cooling time, and initial enrichment) and then were used to determine those same quantities in each measured spent fuel assembly. Finally, the results obtained in comparison with the operator declared values, as well as the methodology developed, are discussed in detail in the paper.},

  doi          = {10.1016/j.nima.2016.02.072},

  journal      = {Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment},

  number       = ,

  volume       = 820,

  place        = {United States},

  year         = {Fri Feb 26 00:00:00 EST 2016},

  month        = {Fri Feb 26 00:00:00 EST 2016}

}

Copy to clipboard

Journal Article:

Free Publicly Available Full Text

Accepted Manuscript (Publisher)

Accepted Manuscript (DOE)

Publisher's Version of Record

https://doi.org/10.1016/j.nima.2016.02.072

Other availability

Search WorldCat to find libraries that may hold this journal

Citation Metrics:

Cited by: 27 works

Citation information provided by
Web of Science

Save / Share:

Export Metadata

Save to My Library

Similar Records in DOE PAGES and OSTI.GOV collections:

Passive gamma analysis of the boiling-water-reactor assemblies

Journal Article Vo, D. ; Favalli, A. ; Grogan, B. ; ... - Nuclear Instruments and Methods in Physics Research. Section A, Accelerators, Spectrometers, Detectors and Associated Equipment

This research focused on the analysis of a set of stationary passive gamma measurements taken on the spent nuclear fuel assemblies froma boiling water reactor (BWR) using pulse height analysis data acquisition. The measurements were performed on 25 different BWR assemblies in 2014 at Sweden's Central Interim Storage Facility for Spent Nuclear Fuel (Clab). This study was performed as part of the Next Generation of Safeguards Initiative Spent Fuel project to research the application of nondestructive assay (NDA) to spent fuel assemblies. The NGSI SF team is working to achieve the following technical goals moreeasily and efficiently than in themore »« less
Cited by 2
https://doi.org/10.1016/j.nima.2016.06.013

Full Text Available
Partial Defect Verification of Spent Fuel Assemblies by PDET: Principle and Field Testing in Interim Spent Fuel Storage Facility (CLAB) in Sweden

Conference Ham, Y. S. ; Kerr, P. ; Sitaraman, S. ; ...

The need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called 'difficult-to-access' areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into 'difficult-to-access' areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reported themore »« less
https://doi.org/10.1109/ANIMMA.2015.7465608
Partial defect verification of spent fuel assemblies by PDET: Principle and field testing in Interim Spent fuel Storage Facility (CLAB) in Sweden

Journal Article Ham, Y. ; Kerr, P. ; Sitaraman, S. ; ... - Institute of Electrical and Electronics Engineers, na, na, May 5, 2015, pp. 1-7

Here, the need for the development of a credible method and instrument for partial defect verification of spent fuel has been emphasized over a few decades in the safeguards communities as the diverted spent fuel pins can be the source of nuclear terrorism or devices. The need is increasingly more important and even urgent as many countries have started to transfer spent fuel to so called "difficult-to-access" areas such as dry storage casks, reprocessing or geological repositories. Partial defect verification is required by IAEA before spent fuel is placed into "difficult-to-access" areas. Earlier, Lawrence Livermore National Laboratory (LLNL) has reportedmore »« less
https://doi.org/10.1109/ANIMMA.2015.7465608

Full Text Available
Fresh Fuel Measurements With the Differential Die-Away Self-Interrogation Instrument

Journal Article Trahan, Alexis C. ; Belian, Anthony P. ; Swinhoe, Martyn T. ; ... - IEEE Transactions on Nuclear Science

The purpose of the Next Generation Safeguards Initiative (NGSI)-Spent Fuel (SF) Project is to strengthen the technical toolkit of safeguards inspectors and/or other interested parties. Thus the NGSI-SF team is working to achieve the following technical goals more easily and efficiently than in the past using nondestructive assay measurements of spent fuel assemblies: 1) verify the initial enrichment, burnup, and cooling time of facility declaration; 2) detect the diversion or replacement of pins; 3) estimate the plutonium mass; 4) estimate decay heat; and 5) determine the reactivity of spent fuel assemblies. The differential die-away self-interrogation (DDSI) instrument is one instrumentmore »« less
Cited by 1
https://doi.org/10.1109/TNS.2017.2648506

Full Text Available
Nondestructive Assay Data Integration with the SKB-50 Assemblies - FY16 Update

Technical Report Tobin, Stephen Joseph ; Fugate, Michael Lynn ; Trellue, Holly Renee ; ...

A project to research the application of non-destructive assay (NDA) techniques for spent fuel assemblies is underway at the Central Interim Storage Facility for Spent Nuclear Fuel (for which the Swedish acronym is Clab) in Oskarshamn, Sweden. The research goals of this project contain both safeguards and non-safeguards interests. These nondestructive assay (NDA) technologies are designed to strengthen the technical toolkit of safeguard inspectors and others to determine the following technical goals more accurately; Verify initial enrichment, burnup, and cooling time of facility declaration for spent fuel assemblies; Detect replaced or missing pins from a given spent fuel assembly tomore »« less
https://doi.org/10.2172/1330638

Full Text Available

Similar Records