DOE PAGES title logo U.S. Department of Energy
Office of Scientific and Technical Information

Title: Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel

Abstract

Nuclear forensics has a broad task to characterize recovered nuclear or radiological material and interpret the results of investigation. One approach to isotopic characterization of nuclear material obtained from a reactor is to chemically separate and perform isotopic measurements on the sample and verify the results with modeling of the sample history, for example, operation of a nuclear reactor. The major actinide plutonium and fission product cesium are commonly measured signatures of the fuel history in a reactor core. This study investigates the uncertainty of the plutonium and cesium isotope ratios of a fuel rod discharged from a research pressurized water reactor when the location of the sample is not known a priori. A sensitivity analysis showed overpredicted values for the 240Pu/239Pu ratio toward the axial center of the rod and revealed a lower probability of the rod of interest (ROI) being on the periphery of the assembly. The uncertainty analysis found the relative errors due to only the rod position and boron concentration to be 17% to 36% and 7% to 15% for the 240Pu/239Pu and 137Cs/135Cs ratios, respectively. Lastly, this study provides a method for uncertainty quantification of isotope concentrations due to the location of the ROI. Similarmore » analyses can be performed to verify future chemical and isotopic analyses.« less

Authors:
 [1];  [1];  [2];  [2]
  1. Georgia Inst. of Technology, Atlanta, GA (United States)
  2. Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)
Publication Date:
Research Org.:
Lawrence Livermore National Laboratory (LLNL), Livermore, CA (United States)
Sponsoring Org.:
USDOE
OSTI Identifier:
1411672
Report Number(s):
LLNL-JRNL-681885
Journal ID: ISSN 0029-5450
Grant/Contract Number:  
AC52-07NA27344
Resource Type:
Accepted Manuscript
Journal Name:
Nuclear Technology
Additional Journal Information:
Journal Volume: 197; Journal Issue: 1; Journal ID: ISSN 0029-5450
Publisher:
Taylor & Francis - formerly American Nuclear Society (ANS)
Country of Publication:
United States
Language:
English
Subject:
98 NUCLEAR DISARMAMENT, SAFEGUARDS AND PHYSICAL PROTECTION; 11 NUCLEAR FUEL CYCLE AND RUEL MATERIALS; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; forensics; isotope; uncertainty

Citation Formats

Conant, Andrew, Erickson, Anna, Robel, Martin, and Isselhardt, Brett. Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel. United States: N. p., 2017. Web. doi:10.13182/NT16-88.
Conant, Andrew, Erickson, Anna, Robel, Martin, & Isselhardt, Brett. Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel. United States. https://doi.org/10.13182/NT16-88
Conant, Andrew, Erickson, Anna, Robel, Martin, and Isselhardt, Brett. Fri . "Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel". United States. https://doi.org/10.13182/NT16-88. https://www.osti.gov/servlets/purl/1411672.
@article{osti_1411672,
title = {Sensitivity and Uncertainty Analysis of Plutonium and Cesium Isotopes in Modeling of BR3 Reactor Spent Fuel},
author = {Conant, Andrew and Erickson, Anna and Robel, Martin and Isselhardt, Brett},
abstractNote = {Nuclear forensics has a broad task to characterize recovered nuclear or radiological material and interpret the results of investigation. One approach to isotopic characterization of nuclear material obtained from a reactor is to chemically separate and perform isotopic measurements on the sample and verify the results with modeling of the sample history, for example, operation of a nuclear reactor. The major actinide plutonium and fission product cesium are commonly measured signatures of the fuel history in a reactor core. This study investigates the uncertainty of the plutonium and cesium isotope ratios of a fuel rod discharged from a research pressurized water reactor when the location of the sample is not known a priori. A sensitivity analysis showed overpredicted values for the 240Pu/239Pu ratio toward the axial center of the rod and revealed a lower probability of the rod of interest (ROI) being on the periphery of the assembly. The uncertainty analysis found the relative errors due to only the rod position and boron concentration to be 17% to 36% and 7% to 15% for the 240Pu/239Pu and 137Cs/135Cs ratios, respectively. Lastly, this study provides a method for uncertainty quantification of isotope concentrations due to the location of the ROI. Similar analyses can be performed to verify future chemical and isotopic analyses.},
doi = {10.13182/NT16-88},
journal = {Nuclear Technology},
number = 1,
volume = 197,
place = {United States},
year = {Fri Feb 03 00:00:00 EST 2017},
month = {Fri Feb 03 00:00:00 EST 2017}
}

Journal Article:
Free Publicly Available Full Text
Publisher's Version of Record

Citation Metrics:
Cited by: 4 works
Citation information provided by
Web of Science

Save / Share:

Works referenced in this record:

Burnup studies of spent fuels of varying types and enrichment
journal, August 2007


Propagation of statistical and nuclear data uncertainties in Monte Carlo burn-up calculations
journal, April 2008


MCNP and ORIGEN codes validation by calculating RBMK spent nuclear fuel isotopic composition
journal, January 2005

  • Plukienė, Rita; Plukis, Artūras; Remeikis, Vidmantas
  • Lithuanian Journal of Physics, Vol. 45, Issue 4
  • DOI: 10.3952/lithjphys.45411

Cesium isotope ratios as indicators of nuclear power plant operations
journal, November 2011

  • Delmore, James E.; Snyder, Darin C.; Tranter, Troy
  • Journal of Environmental Radioactivity, Vol. 102, Issue 11
  • DOI: 10.1016/j.jenvrad.2011.06.013

Integrated Nondestructive Assay Systems to Estimate Plutonium in Spent Fuel Assemblies
journal, March 2015

  • Burr, T.; Trellue, H.; Tobin, S.
  • Nuclear Science and Engineering, Vol. 179, Issue 3
  • DOI: 10.13182/NSE14-38

Antineutrino analysis for continuous monitoring of nuclear reactors: Sensitivity study
journal, October 2015

  • Stewart, Christopher; Erickson, Anna
  • Journal of Applied Physics, Vol. 118, Issue 16
  • DOI: 10.1063/1.4934638

Estimation of Error Propagation in Monte-Carlo Burnup Calculations
journal, September 1999

  • Takeda, Toshikazu; Hirokawa, Naoki; Noda, Tomohiro
  • Journal of Nuclear Science and Technology, Vol. 36, Issue 9
  • DOI: 10.1080/18811248.1999.9726262

Analysis of Core Physics Experiments on Fresh and Irradiated BR3 MOX Fuel in REBUS Program
journal, May 2009

  • Yamamoto, Toru; Kawashima, Katsuyuki; Ando, Yoshihira
  • Journal of Nuclear Science and Technology, Vol. 46, Issue 5
  • DOI: 10.1080/18811248.2007.9711556

The Role of Nuclear Forensics in Nuclear Security
journal, March 2014


Nuclear forensic investigations with a focus on plutonium
journal, October 2007


Initial MCNP6 Release Overview - MCNP6 version 1.0
report, June 2013


Investigation of the Self-Interrogation Neutron Resonance Densitometry applied to spent fuel using Monte Carlo simulations
journal, January 2015


Analysis of high burnup pressurized water reactor fuel using uranium, plutonium, neodymium, and cesium isotope correlations with burnup
journal, December 2015

  • Kim, Jung Suk; Jeon, Young Shin; Park, Soon Dal
  • Nuclear Engineering and Technology, Vol. 47, Issue 7
  • DOI: 10.1016/j.net.2015.08.002

Works referencing / citing this record:

Nanoscale Spatially Resolved Mapping of Uranium Enrichment
journal, August 2019