Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors
Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycl...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
He, Liao-Yuan [verfasserIn] Xia, Shao-Peng [verfasserIn] Zhou, Xue-Mei [verfasserIn] Chen, Jin-Gen [verfasserIn] Liu, Gui-Min [verfasserIn] Zou, Yang [verfasserIn] Yan, Rui [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2020 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
Enthalten in: Nuclear science and techniques - Singapore : Springer, 2006, 31(2020), 8 vom: 08. Aug. |
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| Übergeordnetes Werk: |
volume:31 ; year:2020 ; number:8 ; day:08 ; month:08 |
| Links: |
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| DOI / URN: |
10.1007/s41365-020-00790-x |
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| Katalog-ID: |
SPR040584070 |
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| 520 | |a Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. | ||
| 650 | 4 | |a Th–U cycle |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Molten salt fast reactor |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Breeding capability |7 (dpeaa)DE-He213 | |
| 650 | 4 | |a Doubling time |7 (dpeaa)DE-He213 | |
| 700 | 1 | |a Xia, Shao-Peng |e verfasserin |4 aut | |
| 700 | 1 | |a Zhou, Xue-Mei |e verfasserin |4 aut | |
| 700 | 1 | |a Chen, Jin-Gen |e verfasserin |4 aut | |
| 700 | 1 | |a Liu, Gui-Min |e verfasserin |4 aut | |
| 700 | 1 | |a Zou, Yang |e verfasserin |4 aut | |
| 700 | 1 | |a Yan, Rui |e verfasserin |4 aut | |
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10.1007/s41365-020-00790-x doi (DE-627)SPR040584070 (SPR)s41365-020-00790-x-e DE-627 ger DE-627 rakwb eng 620 ASE 620 530 ASE He, Liao-Yuan verfasserin aut Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors 2020 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 Xia, Shao-Peng verfasserin aut Zhou, Xue-Mei verfasserin aut Chen, Jin-Gen verfasserin aut Liu, Gui-Min verfasserin aut Zou, Yang verfasserin aut Yan, Rui verfasserin aut Enthalten in Nuclear science and techniques Singapore : Springer, 2006 31(2020), 8 vom: 08. Aug. (DE-627)513219439 (DE-600)2238719-5 2210-3147 nnns volume:31 year:2020 number:8 day:08 month:08 https://dx.doi.org/10.1007/s41365-020-00790-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 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_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 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_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 31 2020 8 08 08 |
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10.1007/s41365-020-00790-x doi (DE-627)SPR040584070 (SPR)s41365-020-00790-x-e DE-627 ger DE-627 rakwb eng 620 ASE 620 530 ASE He, Liao-Yuan verfasserin aut Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors 2020 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 Xia, Shao-Peng verfasserin aut Zhou, Xue-Mei verfasserin aut Chen, Jin-Gen verfasserin aut Liu, Gui-Min verfasserin aut Zou, Yang verfasserin aut Yan, Rui verfasserin aut Enthalten in Nuclear science and techniques Singapore : Springer, 2006 31(2020), 8 vom: 08. Aug. (DE-627)513219439 (DE-600)2238719-5 2210-3147 nnns volume:31 year:2020 number:8 day:08 month:08 https://dx.doi.org/10.1007/s41365-020-00790-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 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_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 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_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 31 2020 8 08 08 |
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10.1007/s41365-020-00790-x doi (DE-627)SPR040584070 (SPR)s41365-020-00790-x-e DE-627 ger DE-627 rakwb eng 620 ASE 620 530 ASE He, Liao-Yuan verfasserin aut Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors 2020 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 Xia, Shao-Peng verfasserin aut Zhou, Xue-Mei verfasserin aut Chen, Jin-Gen verfasserin aut Liu, Gui-Min verfasserin aut Zou, Yang verfasserin aut Yan, Rui verfasserin aut Enthalten in Nuclear science and techniques Singapore : Springer, 2006 31(2020), 8 vom: 08. Aug. (DE-627)513219439 (DE-600)2238719-5 2210-3147 nnns volume:31 year:2020 number:8 day:08 month:08 https://dx.doi.org/10.1007/s41365-020-00790-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 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_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 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_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 31 2020 8 08 08 |
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10.1007/s41365-020-00790-x doi (DE-627)SPR040584070 (SPR)s41365-020-00790-x-e DE-627 ger DE-627 rakwb eng 620 ASE 620 530 ASE He, Liao-Yuan verfasserin aut Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors 2020 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 Xia, Shao-Peng verfasserin aut Zhou, Xue-Mei verfasserin aut Chen, Jin-Gen verfasserin aut Liu, Gui-Min verfasserin aut Zou, Yang verfasserin aut Yan, Rui verfasserin aut Enthalten in Nuclear science and techniques Singapore : Springer, 2006 31(2020), 8 vom: 08. Aug. (DE-627)513219439 (DE-600)2238719-5 2210-3147 nnns volume:31 year:2020 number:8 day:08 month:08 https://dx.doi.org/10.1007/s41365-020-00790-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 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_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 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_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 31 2020 8 08 08 |
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10.1007/s41365-020-00790-x doi (DE-627)SPR040584070 (SPR)s41365-020-00790-x-e DE-627 ger DE-627 rakwb eng 620 ASE 620 530 ASE He, Liao-Yuan verfasserin aut Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors 2020 Text txt rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 Xia, Shao-Peng verfasserin aut Zhou, Xue-Mei verfasserin aut Chen, Jin-Gen verfasserin aut Liu, Gui-Min verfasserin aut Zou, Yang verfasserin aut Yan, Rui verfasserin aut Enthalten in Nuclear science and techniques Singapore : Springer, 2006 31(2020), 8 vom: 08. Aug. (DE-627)513219439 (DE-600)2238719-5 2210-3147 nnns volume:31 year:2020 number:8 day:08 month:08 https://dx.doi.org/10.1007/s41365-020-00790-x lizenzpflichtig Volltext GBV_USEFLAG_A SYSFLAG_A GBV_SPRINGER GBV_ILN_11 GBV_ILN_20 GBV_ILN_22 GBV_ILN_23 GBV_ILN_24 GBV_ILN_31 GBV_ILN_32 GBV_ILN_39 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_101 GBV_ILN_105 GBV_ILN_110 GBV_ILN_120 GBV_ILN_138 GBV_ILN_150 GBV_ILN_151 GBV_ILN_152 GBV_ILN_161 GBV_ILN_170 GBV_ILN_171 GBV_ILN_187 GBV_ILN_213 GBV_ILN_224 GBV_ILN_230 GBV_ILN_250 GBV_ILN_281 GBV_ILN_285 GBV_ILN_293 GBV_ILN_370 GBV_ILN_602 GBV_ILN_636 GBV_ILN_702 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2004 GBV_ILN_2005 GBV_ILN_2006 GBV_ILN_2007 GBV_ILN_2008 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_2031 GBV_ILN_2034 GBV_ILN_2037 GBV_ILN_2038 GBV_ILN_2039 GBV_ILN_2044 GBV_ILN_2048 GBV_ILN_2049 GBV_ILN_2050 GBV_ILN_2055 GBV_ILN_2056 GBV_ILN_2057 GBV_ILN_2059 GBV_ILN_2061 GBV_ILN_2064 GBV_ILN_2065 GBV_ILN_2068 GBV_ILN_2088 GBV_ILN_2093 GBV_ILN_2106 GBV_ILN_2107 GBV_ILN_2108 GBV_ILN_2110 GBV_ILN_2111 GBV_ILN_2112 GBV_ILN_2113 GBV_ILN_2118 GBV_ILN_2122 GBV_ILN_2129 GBV_ILN_2143 GBV_ILN_2144 GBV_ILN_2147 GBV_ILN_2148 GBV_ILN_2152 GBV_ILN_2153 GBV_ILN_2188 GBV_ILN_2190 GBV_ILN_2232 GBV_ILN_2336 GBV_ILN_2446 GBV_ILN_2470 GBV_ILN_2472 GBV_ILN_2507 GBV_ILN_2522 GBV_ILN_2548 GBV_ILN_4035 GBV_ILN_4037 GBV_ILN_4046 GBV_ILN_4112 GBV_ILN_4125 GBV_ILN_4126 GBV_ILN_4242 GBV_ILN_4246 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_4325 GBV_ILN_4326 GBV_ILN_4328 GBV_ILN_4333 GBV_ILN_4334 GBV_ILN_4335 GBV_ILN_4336 GBV_ILN_4338 GBV_ILN_4393 GBV_ILN_4700 AR 31 2020 8 08 08 |
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Enthalten in Nuclear science and techniques 31(2020), 8 vom: 08. Aug. volume:31 year:2020 number:8 day:08 month:08 |
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Enthalten in Nuclear science and techniques 31(2020), 8 vom: 08. Aug. volume:31 year:2020 number:8 day:08 month:08 |
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Th–U cycle Molten salt fast reactor Breeding capability Doubling time |
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He, Liao-Yuan @@aut@@ Xia, Shao-Peng @@aut@@ Zhou, Xue-Mei @@aut@@ Chen, Jin-Gen @@aut@@ Liu, Gui-Min @@aut@@ Zou, Yang @@aut@@ Yan, Rui @@aut@@ |
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As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. 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| author |
He, Liao-Yuan |
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He, Liao-Yuan ddc 620 misc Th–U cycle misc Molten salt fast reactor misc Breeding capability misc Doubling time Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
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620 ASE 620 530 ASE Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors Th–U cycle (dpeaa)DE-He213 Molten salt fast reactor (dpeaa)DE-He213 Breeding capability (dpeaa)DE-He213 Doubling time (dpeaa)DE-He213 |
| topic |
ddc 620 misc Th–U cycle misc Molten salt fast reactor misc Breeding capability misc Doubling time |
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ddc 620 misc Th–U cycle misc Molten salt fast reactor misc Breeding capability misc Doubling time |
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Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
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Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
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He, Liao-Yuan |
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Nuclear science and techniques |
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He, Liao-Yuan Xia, Shao-Peng Zhou, Xue-Mei Chen, Jin-Gen Liu, Gui-Min Zou, Yang Yan, Rui |
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10.1007/s41365-020-00790-x |
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verfasserin |
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th–u cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
| title_auth |
Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
| abstract |
Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. |
| abstractGer |
Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. |
| abstract_unstemmed |
Abstract The recent development of molten salt fast reactors has generated a renewed interest in them. As compared to traditional solid fuel fast neutron systems, it has many unique advantages, e.g., lower fissile inventory, no initial criticality reserve, waste reduction, and a simplified fuel cycle. It has been recognized as an ideal reactor for achieving a closed Th–U cycle. Based on the carrier salt, molten salt fast reactors could be divided into either a molten chloride salt fast reactor (MCFR) or a molten fluoride salt fast reactor (MFFR); to compare their Th–U cycle performance, the neutronic parameters in a breeding and burning (B&B) transition scenario were studied based on similar core geometry and power. The results demonstrated that the required reprocessing rate for an MCFR to achieve self-breeding was lower than that of an MFFR. Moreover, the breeding capability of an MCFR was better than that of an MFFR; at a reprocessing rate of 40 L/day, using LEU and Pu as start-up fissile materials, the doubling time (DT) of an MFFR and MCFR were 88.0 years and 48.0 years, and 16.5 years and 16.2 years, respectively. Besides, an MCFR has lower radio-toxicity due to lower buildup of fission products (FPs) and transuranium (TRU), while an MFFR has a larger, delayed neutron fraction with smaller changes during the entire operation. |
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| title_short |
Th–U cycle performance analysis based on molten chloride salt and molten fluoride salt fast reactors |
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https://dx.doi.org/10.1007/s41365-020-00790-x |
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Xia, Shao-Peng Zhou, Xue-Mei Chen, Jin-Gen Liu, Gui-Min Zou, Yang Yan, Rui |
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Xia, Shao-Peng Zhou, Xue-Mei Chen, Jin-Gen Liu, Gui-Min Zou, Yang Yan, Rui |
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| doi_str |
10.1007/s41365-020-00790-x |
| up_date |
2024-07-03T16:56:24.034Z |
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|
| score |
7.400736 |