Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning

Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of...
Ausführliche Beschreibung

Gespeichert in:

Autor*in:	Nguyen, Tam Cong [verfasserIn] Van Nguyen, Quan [verfasserIn] Lakosi, Laszlo [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2018

Schlagwörter:	High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor

Übergeordnetes Werk:	Enthalten in: Progress in nuclear energy - Amsterdam [u.a.] : Elsevier Science, 1977, 110, Seite 103-109
Übergeordnetes Werk:	volume:110 ; pages:103-109

DOI / URN:	10.1016/j.pnucene.2018.09.016

Katalog-ID:	ELV001168282

Internformat


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520			\|a Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done.
650		4	\|a High-resolution gamma spectrometry
650		4	\|a Non-destructive analysis
650		4	\|a Nuclear material content
650		4	\|a Spent reactor fuel
650		4	\|a Absorption factor
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700	1		\|a Lakosi, Laszlo \|e verfasserin \|4 aut
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matchkey_str	article:01491970:2018----::eemntoonceraeilotnoiesrgntnfodmgdpnfeasmlebuigol
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publishDate	2018
allfields	10.1016/j.pnucene.2018.09.016 doi (DE-627)ELV001168282 (ELSEVIER)S0149-1970(18)30244-0 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Nguyen, Tam Cong verfasserin aut Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done. High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor Van Nguyen, Quan verfasserin aut Lakosi, Laszlo verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 110, Seite 103-109 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:110 pages:103-109 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 52.50 Energietechnik: Allgemeines AR 110 103-109
spelling	10.1016/j.pnucene.2018.09.016 doi (DE-627)ELV001168282 (ELSEVIER)S0149-1970(18)30244-0 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Nguyen, Tam Cong verfasserin aut Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done. High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor Van Nguyen, Quan verfasserin aut Lakosi, Laszlo verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 110, Seite 103-109 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:110 pages:103-109 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 52.50 Energietechnik: Allgemeines AR 110 103-109
allfields_unstemmed	10.1016/j.pnucene.2018.09.016 doi (DE-627)ELV001168282 (ELSEVIER)S0149-1970(18)30244-0 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Nguyen, Tam Cong verfasserin aut Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done. High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor Van Nguyen, Quan verfasserin aut Lakosi, Laszlo verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 110, Seite 103-109 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:110 pages:103-109 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 52.50 Energietechnik: Allgemeines AR 110 103-109
allfieldsGer	10.1016/j.pnucene.2018.09.016 doi (DE-627)ELV001168282 (ELSEVIER)S0149-1970(18)30244-0 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Nguyen, Tam Cong verfasserin aut Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done. High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor Van Nguyen, Quan verfasserin aut Lakosi, Laszlo verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 110, Seite 103-109 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:110 pages:103-109 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 52.50 Energietechnik: Allgemeines AR 110 103-109
allfieldsSound	10.1016/j.pnucene.2018.09.016 doi (DE-627)ELV001168282 (ELSEVIER)S0149-1970(18)30244-0 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Nguyen, Tam Cong verfasserin aut Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done. High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor Van Nguyen, Quan verfasserin aut Lakosi, Laszlo verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 110, Seite 103-109 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:110 pages:103-109 GBV_USEFLAG_U SYSFLAG_U GBV_ELV GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_40 GBV_ILN_60 GBV_ILN_62 GBV_ILN_63 GBV_ILN_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_224 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2008 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2038 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4325 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4338 GBV_ILN_4393 52.50 Energietechnik: Allgemeines AR 110 103-109
language	English
source	Enthalten in Progress in nuclear energy 110, Seite 103-109 volume:110 pages:103-109
sourceStr	Enthalten in Progress in nuclear energy 110, Seite 103-109 volume:110 pages:103-109
format_phy_str_mv	Article
bklname	Energietechnik: Allgemeines
institution	findex.gbv.de
topic_facet	High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor
dewey-raw	620
isfreeaccess_bool	false
container_title	Progress in nuclear energy
authorswithroles_txt_mv	Nguyen, Tam Cong @@aut@@ Van Nguyen, Quan @@aut@@ Lakosi, Laszlo @@aut@@
publishDateDaySort_date	2018-01-01T00:00:00Z
hierarchy_top_id	320412032
dewey-sort	3620
id	ELV001168282
language_de	englisch
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author	Nguyen, Tam Cong
spellingShingle	Nguyen, Tam Cong ddc 620 bkl 52.50 misc High-resolution gamma spectrometry misc Non-destructive analysis misc Nuclear material content misc Spent reactor fuel misc Absorption factor Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
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topic_title	620 DE-600 52.50 bkl Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning High-resolution gamma spectrometry Non-destructive analysis Nuclear material content Spent reactor fuel Absorption factor
topic	ddc 620 bkl 52.50 misc High-resolution gamma spectrometry misc Non-destructive analysis misc Nuclear material content misc Spent reactor fuel misc Absorption factor
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title	Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
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title_full	Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
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title_sort	determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
title_auth	Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
abstract	Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done.
abstractGer	Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done.
abstract_unstemmed	Correlation of the fission product Cs-137, U, and Pu with burn-up has been used to develop a method for determining the U and Pu contents of items originating from 30 spent fuel assemblies (SFAs), which became unusable due to an event in 2003 at Paks Nuclear Power Plant (NPP), Hungary. A mixture of broken fuel rods, pellets, and parts of the cladding were repacked into 72 canisters, whose nuclear material content was to be determined. In this paper, the method has been updated for scanning Cs137 activity and the Cs134/Cs137 ratio along the canisters in 100 s real time intervals by an HPGe detector using a narrow collimator. The effect of mixed burn-up and the irregular fuel geometry was taken into account by using the so-called infinite energy method. The absorption correction factor seems to be constant for all canisters. This is probably due to the overwhelming effect of the thick absorbing water layer in front of canisters lowered down into the service pit, where the measurements were done.
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title_short	Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning
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up_date	2024-07-06T20:27:23.840Z
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Determination of nuclear material content of items originating from damaged spent fuel assemblies by using collimated gamma-spectrometric scanning

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