Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology
Härtill 5 uppsatser Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004 filosofie doktorsexamen Doctor philosophiae Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fue...
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creator | Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics |
description | Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of |
format | Dissertation |
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Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
degree of Doctor of Philosophy
Docteur ès lettres
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
degree of Doctor of Philosophy
Docteur ès lettres
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala</description><language>eng ; swe</language><publisher>Acta Universitatis Upsaliensis</publisher><creationdate>2004</creationdate><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://data.europeana.eu/item/9200111/BibliographicResource_1000085929510$$EHTML$$P50$$Geuropeana$$Hfree_for_read</linktohtml><link.rule.ids>311,780,38517,76176</link.rule.ids><linktorsrc>$$Uhttps://data.europeana.eu/item/9200111/BibliographicResource_1000085929510$$EView_record_in_Europeana$$FView_record_in_$$GEuropeana$$Hfree_for_read</linktorsrc></links><search><creatorcontrib>Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik</creatorcontrib><creatorcontrib>Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics</creatorcontrib><title>Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology</title><description>Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
degree of Doctor of Philosophy
Docteur ès lettres
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
degree of Doctor of Philosophy
Docteur ès lettres
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala</description><fulltext>true</fulltext><rsrctype>dissertation</rsrctype><creationdate>2004</creationdate><recordtype>dissertation</recordtype><sourceid>1GC</sourceid><recordid>eNqtjEsKwjAUALtxIeod3gWEpFKwW6ula1tXLsozvraBJC8kqeDt_eARnM1shllm14qtDzSRi_pB0M7WYtAUgQe4eB_RIBx1jBQSJs0uwhDYQpoIalSzSc9P2SpNThGgu0NHanJseHyus8WAJtLm51XW1KeuarY0B_aEDnvFxpD6jvsyF0JK2R_0zWgeA_pJqzNFnoOiXoo3-6LMy0KK3R9XL_pJV5g</recordid><startdate>20040421</startdate><enddate>20040421</enddate><creator>Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik</creator><creator>Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics</creator><general>Acta Universitatis Upsaliensis</general><scope>1GC</scope></search><sort><creationdate>20040421</creationdate><title>Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology</title><author>Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik ; Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-europeana_collections_9200111_BibliographicResource_10000859295103</frbrgroupid><rsrctype>dissertations</rsrctype><prefilter>dissertations</prefilter><language>eng ; swe</language><creationdate>2004</creationdate><toplevel>online_resources</toplevel><creatorcontrib>Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik</creatorcontrib><creatorcontrib>Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics</creatorcontrib><collection>Europeana Collections</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>Jacobsson Svärd Staffan 1970- , Uppsala universitet, Institutionen för kärn- och partikelfysik</au><au>Jacobsson Svärd Staffan 1970-, Uppsala University, Department of Nuclear and Particle Physics</au><format>dissertation</format><genre>dissertation</genre><ristype>THES</ristype><Advisor>Uppsala universitet Teknisk-naturvetenskapliga vetenskapsområdet Fysiska sektionen Institutionen för kärn- och partikelfysik</Advisor><Advisor>van der Meer Klaas M.Sc</Advisor><Advisor>Håkansson Ane Docent</Advisor><Advisor>Uppsala University The field of science and technology The physical section Department of nuclear and particle physics</Advisor><Advisor>Bäcklin Anders Professor</Advisor><btitle>Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology</btitle><date>2004-04-21</date><risdate>2004</risdate><abstract>Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
degree of Doctor of Philosophy
Docteur ès lettres
The fuel assemblies used at the Swedish nuclear power plants contain typically between 100 and 300 fuel rods. An experimental technique has been demanded for determining the relative activities of specific isotopes in individual fuel rods without dismantling the assemblies. The purpose is to validate production codes, which requires an experimental relative accuracy of <2 % (1 σ).
Therefore, a new, non-destructive tomographic measurement technique for irradiated nuclear fuel assemblies has been developed. The technique includes two main steps: (1) the gamma-ray flux distribution around the assembly is recorded, and (2) the interior gamma-ray source distribution in the assembly is reconstructed. The use of detailed gamma-ray transport calculations in the reconstruction procedure enables accurate determination of the relative rod-by-rod source distribution.
To investigate the accuracy achievable, laboratory equipment has been constructed, including a fuel model with a well-known distribution of 137 Cs. Furthermore, an instrument has been constructed and built for in-pool measurements on irradiated fuel assemblies at nuclear power plants.
Using the laboratory equipment, a relative accuracy of 1.2 % was obtained (1 σ). The measurements on irradiated fuel resulted in a repeatability of 0.8 %, showing the accuracy that can be achieved using this instrument. The agreement between rod-by-rod data obtained in calculations using the POLCA–7 production code and measured data was 3.1 % (1 σ).
Additionally, there is a safeguards interest in the tomographic technique for verifying that no fissile material has been diverted from fuel assemblies, i.e. that no fuel rods have been removed or replaced. The applicability has been demonstrated in a measurement on a spent fuel assembly. Furthermore, detection of both the removal of a rod as well as the replacement with a non-active rod has been investigated in detail and quantitatively established using the laboratory equipment.
Härtill 5 uppsatser
Diss. (sammanfattning) Uppsala : Uppsala universitet, 2004
filosofie doktorsexamen
Doctor philosophiae
degree of Doctor of Philosophy
Docteur ès lettres
Häggsalen, Ångströmlaboratoriet, Lägerhyddsvägen 1, Polacksbacken, Uppsala</abstract><pub>Acta Universitatis Upsaliensis</pub><oa>free_for_read</oa></addata></record> |
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title | Comprehensive Summaries of Uppsala Dissertations from the Faculty of Science and Technology |
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