Ratio tests of dosimetry cross-sections for 93Nb(n,2n)92mNb and 197Au(n,2n)196Au to 27Al(n,α)24Na reactions

Iwasaki, S.; Sakuma, M.; Odano, Naoteru; Suda, H.; Sugiyama, K.

doi:10.1016/0149-1970(91)90037-p

Cited by 3 publications

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“…This decision may not correctly reflect the covariance in cases where new experimental data have resulted in significant changes in the evaluation. Second, the IRDF-90 library evaluations were often based on the application of a statistical methodology with careful selection/renormalization of experimental data [17,18], while the JENDL-3 Dosimetry Library was often based on fitting of theoretical model calculations to the experimental data [19].…”

Section: Comparison Of Cross Section Evaluationsmentioning

confidence: 99%

SNL RML recommended dosimetry cross section compendium

Griffin¹,

Kelly²,

Luera

et al. 1993

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A compendium of dosimetry cross sections is presented for use in the characterization of fission reactor spectrum and fluence. The contents of this cross section library are based upon the ENDF/B-VI and IRDF-90 cross section libraries and are recommended as a replacement for the DOSCROS84 multigroup library that is widely used by the dosimetry community. Documentation is provided on the rationale for the choice of the cross sections selected for inclusion in this library and on the uncertainty and variation in cross sections presented by state-of-the-art evaluations. MASTEB Acknowledgment The authorsthankDavid W. Vehar,supervisorof the Radiation Metrology La0oratory,for consultation and advice in makingthe formatandcontentof this cross section compendium supportboth the dosimetrist and the reactor experimenter. We also thank CharlesV. Holm for providingthe highest qualityfoil activities and experimental supportfor fielding dosimetry sensors. High qualitydosimetry sensor readingswere critical in allowing the authorsto judge the consistency and accuracyof the cross sections provided in this compendium.

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Section: Comparison Of Cross Section Evaluationsmentioning

confidence: 99%

SNL RML recommended dosimetry cross section compendium

Griffin¹,

Kelly²,

Luera

et al. 1993

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show abstract

“…This decision may not correctly reflect the covariance in cases where new experimental data have resulted in significant changes in the evaluation. Second, whereas some evaluations, such as the IRDF-90 library,were often based on the application of a statistical methodology with careful selection/renormalization of experimental data [23,24], theJENDL-3 Dosimetry librarywas often based on fittingof theoretical model calculations to the experimental data [25].…”

Section: Endl-3 Dosimetrymentioning

confidence: 99%

Status of Neutron Dosimetry Cross Sections

Griffin

Kelly

1994

Reactor Dosimetry

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Several new cross section libraries,such as ENDF/B-VI (release 2), IRDF-90, JEF-2.2, and JENDL-3 Dosimetry, have recentlybeen made availableto the dosimetrycommunity. The SandiaNational Laboratories(SNL) RadiationMetrology Laboratory(RML) has worked with these libraries since pre-release ve;sions were available. This papersummarizes theresults of the intercomparisonand testing of dosimetry cross sections. As a result of this analysis, a compendium of the best dosimetry cross sections was assembled from the available librariesfor use within the SNL RML. This library,referredto as the SN-LRML Library,contains 66 general dosimetry sensors and3 special dosimetersunique to the RML sensor inventory. The SNLRML cross sections have been put into a formatcompatible with commonly used spectrum determinationcodes. Several new cross section librarieshave been made available to the dosimetry community. These include the ENDF/B-VI [1,2], the InternationalReactorDosimetry File (IRDF-90) [3], the JapaneseEvaluated Nuclear Data Library(JENDL-3) [4], the USSR EvaluatedNeutron Data Library(BROND) [5], the Joint EvaluatedFile (JEF-2.2) [6], anupdatedORNL GLUCS [7] evaluation, InternationalLibraryof Neu-tronActivation CrossSection Data for Fusion ReactorApplications(FENDL-2) [8], andChinese Evaluated Nuclear Data Library(CENDL) [9,10]. Table1 summarizes theavailable libraries, comments on the scope of thelibraryandthe issue date. Throughtheiruse as activationsensors for determiningneutronspectraand fluence, these new dosimetry cross sections affect the characterizationof neutron radiationdamage facilities, the use of monitor foils to relate a given device irradiationto the specified environment, the comparison of device damage between reactor facilities, and the comparison of radiation-hardening test environments with anticipatedoperatingenvironments. The Sandia National Laboratories(SNL) Radiation Metrology Laboratory (RML) has worked with versions of these cross sections since pre-release datawere available. These new cross sections have been comparedwith each other andevaluated with respect to their accuracyand consistency for spectrum unfolding applications. A compendium of dosimetry cross sections was assembled for use within the SNL RadiationMetrology Laboratory.This library, referredto as the SNLRMLlibrary [11],was empiricallytest-1Senior Member of the Technical Staff,

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Calculation of Cobalt and Gold Dosimetry Cross Sections from 1 to 50 MeV

Iwasaki

Odano

1994

Reactor Dosimetry

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Dosimetry cross sections for cobalt and gold are evaluated by the theoretical model based method to 50 MeV for the application to accelerator-based high energy neutron fields. We employed a model code system, SINCROS-II whose main part is a modified version of GNASH. Appropriate model parameters were selected or determined by fitting the cross sections to the available data mainly below 20 MeV. The calculations were extended to 50 MeV using these parameters. For the cobalt, the activation dosimetry reactions (n,2n), (n,3n), (n,4n), (n,p), (n,α) and (n,α2n), and a-production reaction (n,He) and for the gold, (n,2n), (n,3n), (n,4n) and (n,p), (n,ot) = (n,He) cross sections were calculated. Consistency of the these calculated cross sections is discussed by comparing with a few available experimental data above 20 MeV. Particular emphasis is placed on the consistency of the cobalt cross sections. The reaction 59Co(n,α2n) can be a new promising dosimetry one between 30 and 50 MeV.

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Ratio tests of dosimetry cross-sections for 93Nb(n,2n)92mNb and 197Au(n,2n)196Au to 27Al(n,α)24Na reactions

Cited by 3 publications

References 0 publications

SNL RML recommended dosimetry cross section compendium

SNL RML recommended dosimetry cross section compendium

Status of Neutron Dosimetry Cross Sections

Calculation of Cobalt and Gold Dosimetry Cross Sections from 1 to 50 MeV

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