Simultaneous statistical analysis of large arrays of correlated neutron measurements
Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented....
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Badikov, S. A. [verfasserIn] |
|---|
| Format: |
Artikel |
|---|---|
| Sprache: |
Englisch |
| Erschienen: |
2000 |
|---|
| Schlagwörter: |
|---|
| Anmerkung: |
© Kluwer Academic/Plenum Publishers 2000 |
|---|
| Übergeordnetes Werk: |
Enthalten in: Atomic energy - Kluwer Academic Publishers-Plenum Publishers, 1992, 88(2000), 3 vom: März, Seite 200-205 |
|---|---|
| Übergeordnetes Werk: |
volume:88 ; year:2000 ; number:3 ; month:03 ; pages:200-205 |
| Links: |
|---|
| DOI / URN: |
10.1007/BF02673160 |
|---|
| Katalog-ID: |
OLC206085265X |
|---|
| LEADER | 01000caa a22002652 4500 | ||
|---|---|---|---|
| 001 | OLC206085265X | ||
| 003 | DE-627 | ||
| 005 | 20230502214435.0 | ||
| 007 | tu | ||
| 008 | 200820s2000 xx ||||| 00| ||eng c | ||
| 024 | 7 | |a 10.1007/BF02673160 |2 doi | |
| 035 | |a (DE-627)OLC206085265X | ||
| 035 | |a (DE-He213)BF02673160-p | ||
| 040 | |a DE-627 |b ger |c DE-627 |e rakwb | ||
| 041 | |a eng | ||
| 082 | 0 | 4 | |a 530 |q VZ |
| 100 | 1 | |a Badikov, S. A. |e verfasserin |4 aut | |
| 245 | 1 | 0 | |a Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| 264 | 1 | |c 2000 | |
| 336 | |a Text |b txt |2 rdacontent | ||
| 337 | |a ohne Hilfsmittel zu benutzen |b n |2 rdamedia | ||
| 338 | |a Band |b nc |2 rdacarrier | ||
| 500 | |a © Kluwer Academic/Plenum Publishers 2000 | ||
| 520 | |a Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. | ||
| 650 | 4 | |a Radiative Capture | |
| 650 | 4 | |a Neutron Cross Section | |
| 650 | 4 | |a Neutron Data | |
| 650 | 4 | |a Fission Cross Section | |
| 650 | 4 | |a High Neutron Energy | |
| 700 | 1 | |a Gai, E. V. |4 aut | |
| 700 | 1 | |a Rabotnov, N. S. |4 aut | |
| 773 | 0 | 8 | |i Enthalten in |t Atomic energy |d Kluwer Academic Publishers-Plenum Publishers, 1992 |g 88(2000), 3 vom: März, Seite 200-205 |w (DE-627)17102916X |w (DE-600)1142004-2 |w (DE-576)033040583 |x 1063-4258 |7 nnns |
| 773 | 1 | 8 | |g volume:88 |g year:2000 |g number:3 |g month:03 |g pages:200-205 |
| 856 | 4 | 1 | |u https://doi.org/10.1007/BF02673160 |z lizenzpflichtig |3 Volltext |
| 912 | |a GBV_USEFLAG_A | ||
| 912 | |a SYSFLAG_A | ||
| 912 | |a GBV_OLC | ||
| 912 | |a SSG-OLC-TEC | ||
| 912 | |a SSG-OLC-PHY | ||
| 912 | |a GBV_ILN_70 | ||
| 912 | |a GBV_ILN_2014 | ||
| 951 | |a AR | ||
| 952 | |d 88 |j 2000 |e 3 |c 03 |h 200-205 | ||
| author_variant |
s a b sa sab e v g ev evg n s r ns nsr |
|---|---|
| matchkey_str |
article:10634258:2000----::iutnosttsiaaayiolrerasforlt |
| hierarchy_sort_str |
2000 |
| publishDate |
2000 |
| allfields |
10.1007/BF02673160 doi (DE-627)OLC206085265X (DE-He213)BF02673160-p DE-627 ger DE-627 rakwb eng 530 VZ Badikov, S. A. verfasserin aut Simultaneous statistical analysis of large arrays of correlated neutron measurements 2000 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic/Plenum Publishers 2000 Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy Gai, E. V. aut Rabotnov, N. S. aut Enthalten in Atomic energy Kluwer Academic Publishers-Plenum Publishers, 1992 88(2000), 3 vom: März, Seite 200-205 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:88 year:2000 number:3 month:03 pages:200-205 https://doi.org/10.1007/BF02673160 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 AR 88 2000 3 03 200-205 |
| spelling |
10.1007/BF02673160 doi (DE-627)OLC206085265X (DE-He213)BF02673160-p DE-627 ger DE-627 rakwb eng 530 VZ Badikov, S. A. verfasserin aut Simultaneous statistical analysis of large arrays of correlated neutron measurements 2000 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic/Plenum Publishers 2000 Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy Gai, E. V. aut Rabotnov, N. S. aut Enthalten in Atomic energy Kluwer Academic Publishers-Plenum Publishers, 1992 88(2000), 3 vom: März, Seite 200-205 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:88 year:2000 number:3 month:03 pages:200-205 https://doi.org/10.1007/BF02673160 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 AR 88 2000 3 03 200-205 |
| allfields_unstemmed |
10.1007/BF02673160 doi (DE-627)OLC206085265X (DE-He213)BF02673160-p DE-627 ger DE-627 rakwb eng 530 VZ Badikov, S. A. verfasserin aut Simultaneous statistical analysis of large arrays of correlated neutron measurements 2000 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic/Plenum Publishers 2000 Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy Gai, E. V. aut Rabotnov, N. S. aut Enthalten in Atomic energy Kluwer Academic Publishers-Plenum Publishers, 1992 88(2000), 3 vom: März, Seite 200-205 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:88 year:2000 number:3 month:03 pages:200-205 https://doi.org/10.1007/BF02673160 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 AR 88 2000 3 03 200-205 |
| allfieldsGer |
10.1007/BF02673160 doi (DE-627)OLC206085265X (DE-He213)BF02673160-p DE-627 ger DE-627 rakwb eng 530 VZ Badikov, S. A. verfasserin aut Simultaneous statistical analysis of large arrays of correlated neutron measurements 2000 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic/Plenum Publishers 2000 Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy Gai, E. V. aut Rabotnov, N. S. aut Enthalten in Atomic energy Kluwer Academic Publishers-Plenum Publishers, 1992 88(2000), 3 vom: März, Seite 200-205 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:88 year:2000 number:3 month:03 pages:200-205 https://doi.org/10.1007/BF02673160 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 AR 88 2000 3 03 200-205 |
| allfieldsSound |
10.1007/BF02673160 doi (DE-627)OLC206085265X (DE-He213)BF02673160-p DE-627 ger DE-627 rakwb eng 530 VZ Badikov, S. A. verfasserin aut Simultaneous statistical analysis of large arrays of correlated neutron measurements 2000 Text txt rdacontent ohne Hilfsmittel zu benutzen n rdamedia Band nc rdacarrier © Kluwer Academic/Plenum Publishers 2000 Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy Gai, E. V. aut Rabotnov, N. S. aut Enthalten in Atomic energy Kluwer Academic Publishers-Plenum Publishers, 1992 88(2000), 3 vom: März, Seite 200-205 (DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 1063-4258 nnns volume:88 year:2000 number:3 month:03 pages:200-205 https://doi.org/10.1007/BF02673160 lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 AR 88 2000 3 03 200-205 |
| language |
English |
| source |
Enthalten in Atomic energy 88(2000), 3 vom: März, Seite 200-205 volume:88 year:2000 number:3 month:03 pages:200-205 |
| sourceStr |
Enthalten in Atomic energy 88(2000), 3 vom: März, Seite 200-205 volume:88 year:2000 number:3 month:03 pages:200-205 |
| format_phy_str_mv |
Article |
| institution |
findex.gbv.de |
| topic_facet |
Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy |
| dewey-raw |
530 |
| isfreeaccess_bool |
false |
| container_title |
Atomic energy |
| authorswithroles_txt_mv |
Badikov, S. A. @@aut@@ Gai, E. V. @@aut@@ Rabotnov, N. S. @@aut@@ |
| publishDateDaySort_date |
2000-03-01T00:00:00Z |
| hierarchy_top_id |
17102916X |
| dewey-sort |
3530 |
| id |
OLC206085265X |
| language_de |
englisch |
| fullrecord |
<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">OLC206085265X</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20230502214435.0</controlfield><controlfield tag="007">tu</controlfield><controlfield tag="008">200820s2000 xx ||||| 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1007/BF02673160</subfield><subfield code="2">doi</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)OLC206085265X</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-He213)BF02673160-p</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">530</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Badikov, S. A.</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Simultaneous statistical analysis of large arrays of correlated neutron measurements</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2000</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">ohne Hilfsmittel zu benutzen</subfield><subfield code="b">n</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Band</subfield><subfield code="b">nc</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">© Kluwer Academic/Plenum Publishers 2000</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references.</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Radiative Capture</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Neutron Cross Section</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Neutron Data</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Fission Cross Section</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">High Neutron Energy</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Gai, E. V.</subfield><subfield code="4">aut</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Rabotnov, N. S.</subfield><subfield code="4">aut</subfield></datafield><datafield tag="773" ind1="0" ind2="8"><subfield code="i">Enthalten in</subfield><subfield code="t">Atomic energy</subfield><subfield code="d">Kluwer Academic Publishers-Plenum Publishers, 1992</subfield><subfield code="g">88(2000), 3 vom: März, Seite 200-205</subfield><subfield code="w">(DE-627)17102916X</subfield><subfield code="w">(DE-600)1142004-2</subfield><subfield code="w">(DE-576)033040583</subfield><subfield code="x">1063-4258</subfield><subfield code="7">nnns</subfield></datafield><datafield tag="773" ind1="1" ind2="8"><subfield code="g">volume:88</subfield><subfield code="g">year:2000</subfield><subfield code="g">number:3</subfield><subfield code="g">month:03</subfield><subfield code="g">pages:200-205</subfield></datafield><datafield tag="856" ind1="4" ind2="1"><subfield code="u">https://doi.org/10.1007/BF02673160</subfield><subfield code="z">lizenzpflichtig</subfield><subfield code="3">Volltext</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_USEFLAG_A</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SYSFLAG_A</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_OLC</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-TEC</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-PHY</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ILN_70</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ILN_2014</subfield></datafield><datafield tag="951" ind1=" " ind2=" "><subfield code="a">AR</subfield></datafield><datafield tag="952" ind1=" " ind2=" "><subfield code="d">88</subfield><subfield code="j">2000</subfield><subfield code="e">3</subfield><subfield code="c">03</subfield><subfield code="h">200-205</subfield></datafield></record></collection>
|
| author |
Badikov, S. A. |
| spellingShingle |
Badikov, S. A. ddc 530 misc Radiative Capture misc Neutron Cross Section misc Neutron Data misc Fission Cross Section misc High Neutron Energy Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| authorStr |
Badikov, S. A. |
| ppnlink_with_tag_str_mv |
@@773@@(DE-627)17102916X |
| format |
Article |
| dewey-ones |
530 - Physics |
| delete_txt_mv |
keep |
| author_role |
aut aut aut |
| collection |
OLC |
| remote_str |
false |
| illustrated |
Not Illustrated |
| issn |
1063-4258 |
| topic_title |
530 VZ Simultaneous statistical analysis of large arrays of correlated neutron measurements Radiative Capture Neutron Cross Section Neutron Data Fission Cross Section High Neutron Energy |
| topic |
ddc 530 misc Radiative Capture misc Neutron Cross Section misc Neutron Data misc Fission Cross Section misc High Neutron Energy |
| topic_unstemmed |
ddc 530 misc Radiative Capture misc Neutron Cross Section misc Neutron Data misc Fission Cross Section misc High Neutron Energy |
| topic_browse |
ddc 530 misc Radiative Capture misc Neutron Cross Section misc Neutron Data misc Fission Cross Section misc High Neutron Energy |
| format_facet |
Aufsätze Gedruckte Aufsätze |
| format_main_str_mv |
Text Zeitschrift/Artikel |
| carriertype_str_mv |
nc |
| hierarchy_parent_title |
Atomic energy |
| hierarchy_parent_id |
17102916X |
| dewey-tens |
530 - Physics |
| hierarchy_top_title |
Atomic energy |
| isfreeaccess_txt |
false |
| familylinks_str_mv |
(DE-627)17102916X (DE-600)1142004-2 (DE-576)033040583 |
| title |
Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| ctrlnum |
(DE-627)OLC206085265X (DE-He213)BF02673160-p |
| title_full |
Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| author_sort |
Badikov, S. A. |
| journal |
Atomic energy |
| journalStr |
Atomic energy |
| lang_code |
eng |
| isOA_bool |
false |
| dewey-hundreds |
500 - Science |
| recordtype |
marc |
| publishDateSort |
2000 |
| contenttype_str_mv |
txt |
| container_start_page |
200 |
| author_browse |
Badikov, S. A. Gai, E. V. Rabotnov, N. S. |
| container_volume |
88 |
| class |
530 VZ |
| format_se |
Aufsätze |
| author-letter |
Badikov, S. A. |
| doi_str_mv |
10.1007/BF02673160 |
| dewey-full |
530 |
| title_sort |
simultaneous statistical analysis of large arrays of correlated neutron measurements |
| title_auth |
Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| abstract |
Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. © Kluwer Academic/Plenum Publishers 2000 |
| abstractGer |
Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. © Kluwer Academic/Plenum Publishers 2000 |
| abstract_unstemmed |
Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references. © Kluwer Academic/Plenum Publishers 2000 |
| collection_details |
GBV_USEFLAG_A SYSFLAG_A GBV_OLC SSG-OLC-TEC SSG-OLC-PHY GBV_ILN_70 GBV_ILN_2014 |
| container_issue |
3 |
| title_short |
Simultaneous statistical analysis of large arrays of correlated neutron measurements |
| url |
https://doi.org/10.1007/BF02673160 |
| remote_bool |
false |
| author2 |
Gai, E. V. Rabotnov, N. S. |
| author2Str |
Gai, E. V. Rabotnov, N. S. |
| ppnlink |
17102916X |
| mediatype_str_mv |
n |
| isOA_txt |
false |
| hochschulschrift_bool |
false |
| doi_str |
10.1007/BF02673160 |
| up_date |
2024-07-04T02:18:56.927Z |
| _version_ |
1803613148992765952 |
| fullrecord_marcxml |
<?xml version="1.0" encoding="UTF-8"?><collection xmlns="http://www.loc.gov/MARC21/slim"><record><leader>01000caa a22002652 4500</leader><controlfield tag="001">OLC206085265X</controlfield><controlfield tag="003">DE-627</controlfield><controlfield tag="005">20230502214435.0</controlfield><controlfield tag="007">tu</controlfield><controlfield tag="008">200820s2000 xx ||||| 00| ||eng c</controlfield><datafield tag="024" ind1="7" ind2=" "><subfield code="a">10.1007/BF02673160</subfield><subfield code="2">doi</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-627)OLC206085265X</subfield></datafield><datafield tag="035" ind1=" " ind2=" "><subfield code="a">(DE-He213)BF02673160-p</subfield></datafield><datafield tag="040" ind1=" " ind2=" "><subfield code="a">DE-627</subfield><subfield code="b">ger</subfield><subfield code="c">DE-627</subfield><subfield code="e">rakwb</subfield></datafield><datafield tag="041" ind1=" " ind2=" "><subfield code="a">eng</subfield></datafield><datafield tag="082" ind1="0" ind2="4"><subfield code="a">530</subfield><subfield code="q">VZ</subfield></datafield><datafield tag="100" ind1="1" ind2=" "><subfield code="a">Badikov, S. A.</subfield><subfield code="e">verfasserin</subfield><subfield code="4">aut</subfield></datafield><datafield tag="245" ind1="1" ind2="0"><subfield code="a">Simultaneous statistical analysis of large arrays of correlated neutron measurements</subfield></datafield><datafield tag="264" ind1=" " ind2="1"><subfield code="c">2000</subfield></datafield><datafield tag="336" ind1=" " ind2=" "><subfield code="a">Text</subfield><subfield code="b">txt</subfield><subfield code="2">rdacontent</subfield></datafield><datafield tag="337" ind1=" " ind2=" "><subfield code="a">ohne Hilfsmittel zu benutzen</subfield><subfield code="b">n</subfield><subfield code="2">rdamedia</subfield></datafield><datafield tag="338" ind1=" " ind2=" "><subfield code="a">Band</subfield><subfield code="b">nc</subfield><subfield code="2">rdacarrier</subfield></datafield><datafield tag="500" ind1=" " ind2=" "><subfield code="a">© Kluwer Academic/Plenum Publishers 2000</subfield></datafield><datafield tag="520" ind1=" " ind2=" "><subfield code="a">Abstract The problems due primarily to the limitations of modern computers, preventing adoption of modern methods for estimating neutron data in everyday practice and making it difficult to use the estimated data in applied programs, are discussed. Possible solutions of these problems are presented. Specifically, an identity transformation of the statistical functional to be minimized is found: this transformation makes it possible to avoid the construction, storage, and numerical inversion of superlarge covariation matrices of measurement uncertainties. The transformation makes it possible to perform statistical analysis of an arbitrarily large number of measurements. An efficient method of parameterization of the cross sections of neutron reactions at high neutron energy is proposed. The method is based on the use of the Adler-Adler resonance formula for fitting the cross sections. The parameters in the formula in this case do not have a clear physical interpretation. The method makes it possible to decrease substantially the volume of information to be stored in estimated data files in ENDF-6 format. For three cross sections (total, fission, and radiative capture), the proposed parameterization is universal, and it makes it possible to represent the cross section in a single manner from the thermal point up to an arbitrarily high neutron energy. The results of this work are illustrated for estimation of the cross section of the $ reaction^{241} $Am (n,f). 1 figure, 1 table, 27 references.</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Radiative Capture</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Neutron Cross Section</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Neutron Data</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">Fission Cross Section</subfield></datafield><datafield tag="650" ind1=" " ind2="4"><subfield code="a">High Neutron Energy</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Gai, E. V.</subfield><subfield code="4">aut</subfield></datafield><datafield tag="700" ind1="1" ind2=" "><subfield code="a">Rabotnov, N. S.</subfield><subfield code="4">aut</subfield></datafield><datafield tag="773" ind1="0" ind2="8"><subfield code="i">Enthalten in</subfield><subfield code="t">Atomic energy</subfield><subfield code="d">Kluwer Academic Publishers-Plenum Publishers, 1992</subfield><subfield code="g">88(2000), 3 vom: März, Seite 200-205</subfield><subfield code="w">(DE-627)17102916X</subfield><subfield code="w">(DE-600)1142004-2</subfield><subfield code="w">(DE-576)033040583</subfield><subfield code="x">1063-4258</subfield><subfield code="7">nnns</subfield></datafield><datafield tag="773" ind1="1" ind2="8"><subfield code="g">volume:88</subfield><subfield code="g">year:2000</subfield><subfield code="g">number:3</subfield><subfield code="g">month:03</subfield><subfield code="g">pages:200-205</subfield></datafield><datafield tag="856" ind1="4" ind2="1"><subfield code="u">https://doi.org/10.1007/BF02673160</subfield><subfield code="z">lizenzpflichtig</subfield><subfield code="3">Volltext</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_USEFLAG_A</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SYSFLAG_A</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_OLC</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-TEC</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">SSG-OLC-PHY</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ILN_70</subfield></datafield><datafield tag="912" ind1=" " ind2=" "><subfield code="a">GBV_ILN_2014</subfield></datafield><datafield tag="951" ind1=" " ind2=" "><subfield code="a">AR</subfield></datafield><datafield tag="952" ind1=" " ind2=" "><subfield code="d">88</subfield><subfield code="j">2000</subfield><subfield code="e">3</subfield><subfield code="c">03</subfield><subfield code="h">200-205</subfield></datafield></record></collection>
|
| score |
7.4007816 |