Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor

The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that...
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Autor*in:	Bagherzadeh-Atashchi, S. [verfasserIn] Ghal-Eh, N. [verfasserIn] Rahmani, F. [verfasserIn] Izadi-Najafabadi, R. [verfasserIn] Bedenko, S.V. [verfasserIn]

Format:	E-Artikel
Sprache:	Englisch

Erschienen:	2023

Schlagwörter:	Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters

Übergeordnetes Werk:	Enthalten in: Radiation physics and chemistry - Oxford [u.a.] : Pergamon Press, 1977, 215
Übergeordnetes Werk:	volume:215

DOI / URN:	10.1016/j.radphyschem.2023.111368

Katalog-ID:	ELV06558614X

Internformat


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245	1	0	\|a Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
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520			\|a The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min.
650		4	\|a Boron Neutron Capture Therapy (BNCT)
650		4	\|a IRT-T research reactor
650		4	\|a Beam Shaping Assembly (BSA)
650		4	\|a Neutron converter
650		4	\|a In–phantom parameters
700	1		\|a Ghal-Eh, N. \|e verfasserin \|0 (orcid)0000-0003-4315-7828 \|4 aut
700	1		\|a Rahmani, F. \|e verfasserin \|4 aut
700	1		\|a Izadi-Najafabadi, R. \|e verfasserin \|4 aut
700	1		\|a Bedenko, S.V. \|e verfasserin \|4 aut
773	0	8	\|i Enthalten in \|t Radiation physics and chemistry \|d Oxford [u.a.] : Pergamon Press, 1977 \|g 215 \|h Online-Ressource \|w (DE-627)320596486 \|w (DE-600)2019621-0 \|w (DE-576)251938263 \|x 1878-1020 \|7 nnns
773	1	8	\|g volume:215
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912			\|a GBV_ILN_60
912			\|a GBV_ILN_62
912			\|a GBV_ILN_65
912			\|a GBV_ILN_69
912			\|a GBV_ILN_70
912			\|a GBV_ILN_73
912			\|a GBV_ILN_74
912			\|a GBV_ILN_90
912			\|a GBV_ILN_95
912			\|a GBV_ILN_100
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912			\|a GBV_ILN_105
912			\|a GBV_ILN_110
912			\|a GBV_ILN_150
912			\|a GBV_ILN_151
912			\|a GBV_ILN_165
912			\|a GBV_ILN_187
912			\|a GBV_ILN_213
912			\|a GBV_ILN_224
912			\|a GBV_ILN_230
912			\|a GBV_ILN_370
912			\|a GBV_ILN_602
912			\|a GBV_ILN_702
912			\|a GBV_ILN_2001
912			\|a GBV_ILN_2003
912			\|a GBV_ILN_2004
912			\|a GBV_ILN_2005
912			\|a GBV_ILN_2007
912			\|a GBV_ILN_2009
912			\|a GBV_ILN_2010
912			\|a GBV_ILN_2011
912			\|a GBV_ILN_2014
912			\|a GBV_ILN_2015
912			\|a GBV_ILN_2020
912			\|a GBV_ILN_2021
912			\|a GBV_ILN_2025
912			\|a GBV_ILN_2026
912			\|a GBV_ILN_2027
912			\|a GBV_ILN_2034
912			\|a GBV_ILN_2044
912			\|a GBV_ILN_2048
912			\|a GBV_ILN_2049
912			\|a GBV_ILN_2050
912			\|a GBV_ILN_2055
912			\|a GBV_ILN_2056
912			\|a GBV_ILN_2059
912			\|a GBV_ILN_2061
912			\|a GBV_ILN_2064
912			\|a GBV_ILN_2106
912			\|a GBV_ILN_2110
912			\|a GBV_ILN_2111
912			\|a GBV_ILN_2112
912			\|a GBV_ILN_2122
912			\|a GBV_ILN_2129
912			\|a GBV_ILN_2143
912			\|a GBV_ILN_2152
912			\|a GBV_ILN_2153
912			\|a GBV_ILN_2190
912			\|a GBV_ILN_2232
912			\|a GBV_ILN_2336
912			\|a GBV_ILN_2470
912			\|a GBV_ILN_2507
912			\|a GBV_ILN_4035
912			\|a GBV_ILN_4037
912			\|a GBV_ILN_4112
912			\|a GBV_ILN_4125
912			\|a GBV_ILN_4242
912			\|a GBV_ILN_4249
912			\|a GBV_ILN_4251
912			\|a GBV_ILN_4305
912			\|a GBV_ILN_4306
912			\|a GBV_ILN_4307
912			\|a GBV_ILN_4313
912			\|a GBV_ILN_4322
912			\|a GBV_ILN_4323
912			\|a GBV_ILN_4324
912			\|a GBV_ILN_4326
912			\|a GBV_ILN_4333
912			\|a GBV_ILN_4334
912			\|a GBV_ILN_4338
912			\|a GBV_ILN_4393
912			\|a GBV_ILN_4700
936	b	k	\|a 35.15 \|j Radiochemie \|q VZ
936	b	k	\|a 33.40 \|j Kernphysik \|q VZ
951			\|a AR
952			\|d 215

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matchkey_str	article:18781020:2023----::einfemieobcapiainihccanlf
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bklnumber	35.15 33.40
publishDate	2023
allfields	10.1016/j.radphyschem.2023.111368 doi (DE-627)ELV06558614X (ELSEVIER)S0969-806X(23)00614-X DE-627 ger DE-627 rda eng 540 530 VZ 35.15 bkl 33.40 bkl Bagherzadeh-Atashchi, S. verfasserin aut Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min. Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters Ghal-Eh, N. verfasserin (orcid)0000-0003-4315-7828 aut Rahmani, F. verfasserin aut Izadi-Najafabadi, R. verfasserin aut Bedenko, S.V. verfasserin aut Enthalten in Radiation physics and chemistry Oxford [u.a.] : Pergamon Press, 1977 215 Online-Ressource (DE-627)320596486 (DE-600)2019621-0 (DE-576)251938263 1878-1020 nnns volume:215 GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 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_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_165 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.15 Radiochemie VZ 33.40 Kernphysik VZ AR 215
spelling	10.1016/j.radphyschem.2023.111368 doi (DE-627)ELV06558614X (ELSEVIER)S0969-806X(23)00614-X DE-627 ger DE-627 rda eng 540 530 VZ 35.15 bkl 33.40 bkl Bagherzadeh-Atashchi, S. verfasserin aut Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min. Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters Ghal-Eh, N. verfasserin (orcid)0000-0003-4315-7828 aut Rahmani, F. verfasserin aut Izadi-Najafabadi, R. verfasserin aut Bedenko, S.V. verfasserin aut Enthalten in Radiation physics and chemistry Oxford [u.a.] : Pergamon Press, 1977 215 Online-Ressource (DE-627)320596486 (DE-600)2019621-0 (DE-576)251938263 1878-1020 nnns volume:215 GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 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_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_165 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.15 Radiochemie VZ 33.40 Kernphysik VZ AR 215
allfields_unstemmed	10.1016/j.radphyschem.2023.111368 doi (DE-627)ELV06558614X (ELSEVIER)S0969-806X(23)00614-X DE-627 ger DE-627 rda eng 540 530 VZ 35.15 bkl 33.40 bkl Bagherzadeh-Atashchi, S. verfasserin aut Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min. Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters Ghal-Eh, N. verfasserin (orcid)0000-0003-4315-7828 aut Rahmani, F. verfasserin aut Izadi-Najafabadi, R. verfasserin aut Bedenko, S.V. verfasserin aut Enthalten in Radiation physics and chemistry Oxford [u.a.] : Pergamon Press, 1977 215 Online-Ressource (DE-627)320596486 (DE-600)2019621-0 (DE-576)251938263 1878-1020 nnns volume:215 GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 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_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_165 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.15 Radiochemie VZ 33.40 Kernphysik VZ AR 215
allfieldsGer	10.1016/j.radphyschem.2023.111368 doi (DE-627)ELV06558614X (ELSEVIER)S0969-806X(23)00614-X DE-627 ger DE-627 rda eng 540 530 VZ 35.15 bkl 33.40 bkl Bagherzadeh-Atashchi, S. verfasserin aut Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min. Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters Ghal-Eh, N. verfasserin (orcid)0000-0003-4315-7828 aut Rahmani, F. verfasserin aut Izadi-Najafabadi, R. verfasserin aut Bedenko, S.V. verfasserin aut Enthalten in Radiation physics and chemistry Oxford [u.a.] : Pergamon Press, 1977 215 Online-Ressource (DE-627)320596486 (DE-600)2019621-0 (DE-576)251938263 1878-1020 nnns volume:215 GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 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_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_165 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.15 Radiochemie VZ 33.40 Kernphysik VZ AR 215
allfieldsSound	10.1016/j.radphyschem.2023.111368 doi (DE-627)ELV06558614X (ELSEVIER)S0969-806X(23)00614-X DE-627 ger DE-627 rda eng 540 530 VZ 35.15 bkl 33.40 bkl Bagherzadeh-Atashchi, S. verfasserin aut Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor 2023 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min. Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters Ghal-Eh, N. verfasserin (orcid)0000-0003-4315-7828 aut Rahmani, F. verfasserin aut Izadi-Najafabadi, R. verfasserin aut Bedenko, S.V. verfasserin aut Enthalten in Radiation physics and chemistry Oxford [u.a.] : Pergamon Press, 1977 215 Online-Ressource (DE-627)320596486 (DE-600)2019621-0 (DE-576)251938263 1878-1020 nnns volume:215 GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA 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_65 GBV_ILN_69 GBV_ILN_70 GBV_ILN_73 GBV_ILN_74 GBV_ILN_90 GBV_ILN_95 GBV_ILN_100 GBV_ILN_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_150 GBV_ILN_151 GBV_ILN_165 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_370 GBV_ILN_602 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2007 GBV_ILN_2009 GBV_ILN_2010 GBV_ILN_2011 GBV_ILN_2014 GBV_ILN_2015 GBV_ILN_2020 GBV_ILN_2021 GBV_ILN_2025 GBV_ILN_2026 GBV_ILN_2027 GBV_ILN_2034 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2106 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2470 GBV_ILN_2507 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4242 GBV_ILN_4249 GBV_ILN_4251 GBV_ILN_4305 GBV_ILN_4306 GBV_ILN_4307 GBV_ILN_4313 GBV_ILN_4322 GBV_ILN_4323 GBV_ILN_4324 GBV_ILN_4326 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 35.15 Radiochemie VZ 33.40 Kernphysik VZ AR 215
language	English
source	Enthalten in Radiation physics and chemistry 215 volume:215
sourceStr	Enthalten in Radiation physics and chemistry 215 volume:215
format_phy_str_mv	Article
bklname	Radiochemie Kernphysik
institution	findex.gbv.de
topic_facet	Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters
dewey-raw	540
isfreeaccess_bool	false
container_title	Radiation physics and chemistry
authorswithroles_txt_mv	Bagherzadeh-Atashchi, S. @@aut@@ Ghal-Eh, N. @@aut@@ Rahmani, F. @@aut@@ Izadi-Najafabadi, R. @@aut@@ Bedenko, S.V. @@aut@@
publishDateDaySort_date	2023-01-01T00:00:00Z
hierarchy_top_id	320596486
dewey-sort	3540
id	ELV06558614X
language_de	englisch
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author	Bagherzadeh-Atashchi, S.
spellingShingle	Bagherzadeh-Atashchi, S. ddc 540 bkl 35.15 bkl 33.40 misc Boron Neutron Capture Therapy (BNCT) misc IRT-T research reactor misc Beam Shaping Assembly (BSA) misc Neutron converter misc In–phantom parameters Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
authorStr	Bagherzadeh-Atashchi, S.
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topic_title	540 530 VZ 35.15 bkl 33.40 bkl Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor Boron Neutron Capture Therapy (BNCT) IRT-T research reactor Beam Shaping Assembly (BSA) Neutron converter In–phantom parameters
topic	ddc 540 bkl 35.15 bkl 33.40 misc Boron Neutron Capture Therapy (BNCT) misc IRT-T research reactor misc Beam Shaping Assembly (BSA) misc Neutron converter misc In–phantom parameters
topic_unstemmed	ddc 540 bkl 35.15 bkl 33.40 misc Boron Neutron Capture Therapy (BNCT) misc IRT-T research reactor misc Beam Shaping Assembly (BSA) misc Neutron converter misc In–phantom parameters
topic_browse	ddc 540 bkl 35.15 bkl 33.40 misc Boron Neutron Capture Therapy (BNCT) misc IRT-T research reactor misc Beam Shaping Assembly (BSA) misc Neutron converter misc In–phantom parameters
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title	Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
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title_full	Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
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author_browse	Bagherzadeh-Atashchi, S. Ghal-Eh, N. Rahmani, F. Izadi-Najafabadi, R. Bedenko, S.V.
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author-letter	Bagherzadeh-Atashchi, S.
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title_sort	design of beam line for bnct applications in hec-1 channel of irt-t research reactor
title_auth	Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
abstract	The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min.
abstractGer	The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min.
abstract_unstemmed	The feasibility of using the HEC-1 beam port of the IRT-T research reactor to generate an epithermal neutron beam for Boron Neutron Capture Therapy (BNCT) was investigated using MCNPX2.6 Monte Carlo simulation. The reactor was first simulated to design and optimize a Beam Shaping Assembly (BSA) that meets the neutron beam criteria recommended by the International Atomic Energy Agency (IAEA). The suggested BSA configuration consisted of a cylindrical geometry with 25 cm of MgF2 and 15 cm of Fluental® as a moderator, 15 cm of Pb as a reflector, two 5 cm Bi slabs as gamma-ray shields, and 4 mm of 6Li and 5 mm of borated polyethylene sheets as thermal neutron filters. The results showed that the epithermal neutron flux at the BSA exit was 2.3×109 n/cm2.s, and in-phantom dose analysis indicated that the designed beam could be used for the treatment of deep brain tumors within an allowable treatment time of 50 min.
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title_short	Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor
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author2	Ghal-Eh, N. Rahmani, F. Izadi-Najafabadi, R. Bedenko, S.V.
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doi_str	10.1016/j.radphyschem.2023.111368
up_date	2024-07-06T23:32:50.359Z
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Design of beam line for BNCT applications in HEC-1 channel of IRT-T research reactor

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