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Title: Evaluation of kalman filters and genetic algorithms for delayed neutron nondestructive assay data analyses.

Abstract

The ability to nondestructively determine the presence and quantity of fissile/fertile nuclei in various matrices is important in several areas of nuclear applications, including international and domestic safeguards, radioactive waste characterization, and nuclear facility operations. An analysis was performed to determine the feasibility of identifying the masses of individual fissionable isotopes from a cumulative delayed-neutron signal resulting from the neutron irradiation of several uranium and plutonium isotopes. The feasibility of two separate data-processing techniques was studied: Kalman filtering and genetic algorithms. The basis of each technique is reviewed, and the structure of the algorithms as applied to the delayed-neutron analysis problem is presented. The results of parametric studies performed using several variants of the algorithms are presented. The effect of including additional constraining information such as additional measurements and known relative isotopic concentration is discussed. The parametric studies were conducted using simulated delayed-neutron data representative of the cumulative delayed-neutron response following irradiation of a sample containing {sup 238}U, {sup 235}U, {sup 239}Pu, and {sup 240}Pu. The results show that by processing delayed-neutron data representative of two significantly different fissile/fertile fission ratios, both Kalman filters and genetic algorithms are capable of yielding reasonably accurate estimates of the mass of individual isotopesmore » contained in a given assay sample.« less

Authors:
; ;
Publication Date:
Research Org.:
Argonne National Lab. (ANL), Argonne, IL (United States)
OSTI Identifier:
960338
Report Number(s):
ANL/ED/JA-24029
Journal ID: ISSN 0029-5450; NUTYBB; TRN: US200923%%407
DOE Contract Number:
DE-AC02-06CH11357
Resource Type:
Journal Article
Resource Relation:
Journal Name: Nucl. Technol.; Journal Volume: 122; Journal Issue: 1 ; Apr. 1998
Country of Publication:
United States
Language:
ENGLISH
Subject:
12 MANAGEMENT OF RADIOACTIVE WASTES, AND NON-RADIOACTIVE WASTES FROM NUCLEAR FACILITIES; ALGORITHMS; DATA PROCESSING; DELAYED NEUTRONS; DOMESTIC SAFEGUARDS; EVALUATION; FISSION RATIO; GENETICS; IRRADIATION; MATRICES; NEUTRONS; NUCLEI; PLUTONIUM ISOTOPES; PROCESSING; RADIOACTIVE WASTES; URANIUM

Citation Formats

Aumeier, S. E., Forsmann, J. H., and Engineering Division. Evaluation of kalman filters and genetic algorithms for delayed neutron nondestructive assay data analyses.. United States: N. p., 1998. Web.
Aumeier, S. E., Forsmann, J. H., & Engineering Division. Evaluation of kalman filters and genetic algorithms for delayed neutron nondestructive assay data analyses.. United States.
Aumeier, S. E., Forsmann, J. H., and Engineering Division. 1998. "Evaluation of kalman filters and genetic algorithms for delayed neutron nondestructive assay data analyses.". United States. doi:.
@article{osti_960338,
title = {Evaluation of kalman filters and genetic algorithms for delayed neutron nondestructive assay data analyses.},
author = {Aumeier, S. E. and Forsmann, J. H. and Engineering Division},
abstractNote = {The ability to nondestructively determine the presence and quantity of fissile/fertile nuclei in various matrices is important in several areas of nuclear applications, including international and domestic safeguards, radioactive waste characterization, and nuclear facility operations. An analysis was performed to determine the feasibility of identifying the masses of individual fissionable isotopes from a cumulative delayed-neutron signal resulting from the neutron irradiation of several uranium and plutonium isotopes. The feasibility of two separate data-processing techniques was studied: Kalman filtering and genetic algorithms. The basis of each technique is reviewed, and the structure of the algorithms as applied to the delayed-neutron analysis problem is presented. The results of parametric studies performed using several variants of the algorithms are presented. The effect of including additional constraining information such as additional measurements and known relative isotopic concentration is discussed. The parametric studies were conducted using simulated delayed-neutron data representative of the cumulative delayed-neutron response following irradiation of a sample containing {sup 238}U, {sup 235}U, {sup 239}Pu, and {sup 240}Pu. The results show that by processing delayed-neutron data representative of two significantly different fissile/fertile fission ratios, both Kalman filters and genetic algorithms are capable of yielding reasonably accurate estimates of the mass of individual isotopes contained in a given assay sample.},
doi = {},
journal = {Nucl. Technol.},
number = 1 ; Apr. 1998,
volume = 122,
place = {United States},
year = 1998,
month = 4
}
  • The ability to nondestructively determine the presence and quantity of fissile/fertile nuclei in various matrices is important in several areas of nuclear applications, including international and domestic safeguards, radioactive waste characterization, and nuclear facility operations. An analysis was performed to determine the feasibility of identifying the masses of individual fissionable isotopes from a cumulative delayed-neutron signal resulting form the neutron irradiation of several uranium and plutonium isotopes. The feasibility of two separate data-processing techniques was studied: Kalman filtering and genetic algorithms. The basis of each technique is reviewed, and the structure of the algorithms as applied to the delayed-neutron analysismore » problem is presented. The results of parametric studies performed using several variants of the algorithms are presented. The effect of including additional constraining information such as additional measurements and known relative isotopic concentration is discussed. The parametric studies were conducted using simulated delayed-neutron data representative of the cumulative delayed-neutron response following irradiation of a sample containing {sup 238}U, {sup 235}U, {sup 239}Pu, and {sup 240}Pu. The results show that by processing delayed-neutron data representative of two significantly different fissile/fertile fission ratios, both Kalman filters and genetic algorithms are capable of yielding reasonably accurate estimates of the mass of individual isotopes contained in a given assay sample.« less
  • The ability to nondestructively determine the presence and quantity of fissile and fertile nuclei in various matrices is important in several nuclear applications including international and domestics safeguards, radioactive waste characterization and nuclear facility operations. Material irradiation followed by delayed neutron counting is a well known and useful nondestructive assay technique used to determine the fissile-effective content of assay samples. Previous studies have demonstrated the feasibility of using Kalman filters to unfold individual isotopic contributions to delayed neutron measurements resulting from the assay of mixes of uranium and plutonium isotopes. However, the studies in question used simulated measurement data andmore » idealized parameters. We present the results of the Kalman filter analysis of several measurements of U/Pu mixes taken using Argonne National Laboratory's delayed neutron nondestructive assay device. The results demonstrate the use of Kalman filters as a signal processing tool to determine the fissile and fertile isotopic content of an assay sample from the aggregate delayed neutron response following neutron irradiation.« less
  • An innovative liquid-metal reactor, the Integral Fast Reactor (IFR), is being developed at Argonne National Laboratory. One characteristic of the IFR is the fuel cycle closure. Fissile material bred and fissionable material produced in the reactor are recycled back into the reactor. Waste generated during fuel reprocessing will be packaged into special waste canisters and will be shipped to a repository for final disposal. Prior to its removal from the facility, a measurements of the fissile content will be necessary as a part of an overall fissile material inventory accountability system. A particular form of nondestructive assay called delayed neutronmore » nondestructive assay (DNNDA) is being developed to assist in the establishment of an accountability system. A preliminary neutronics investigation for the current DNNDA has been made to assist and verify the characteristics of the design from a neutronic aspect. A 10[sup 11] n/s, 14-MeV neutron source would provide adequate counting statistics for fissile material at the milligram to gram level.« less
  • This paper reports on the problem of simultaneously estimating neutron density and reactivity while operating a nuclear reactor. It is solved by using a bank of Kalman filters as an estimator and applying a probabilistic test to determine which filter of the bank has the best performance.