The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients
The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benc...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Margulis, M. [verfasserIn] Blaise, P. [verfasserIn] Mellier, F. [verfasserIn] Gilad, E. [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2018 |
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| Schlagwörter: |
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| Übergeordnetes Werk: |
Enthalten in: Progress in nuclear energy - Amsterdam [u.a.] : Elsevier Science, 1977, 105, Seite 124-135 |
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| Übergeordnetes Werk: |
volume:105 ; pages:124-135 |
| DOI / URN: |
10.1016/j.pnucene.2018.01.002 |
|---|
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| 245 | 1 | 0 | |a The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients |
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| 520 | |a The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. | ||
| 650 | 4 | |a SNEAK-12B | |
| 650 | 4 | |a Core disruption | |
| 650 | 4 | |a Severe accidents | |
| 650 | 4 | |a LMFBR | |
| 650 | 4 | |a Sensitivity analysis | |
| 650 | 4 | |a Uncertainty analysis | |
| 700 | 1 | |a Blaise, P. |e verfasserin |4 aut | |
| 700 | 1 | |a Mellier, F. |e verfasserin |4 aut | |
| 700 | 1 | |a Gilad, E. |e verfasserin |4 aut | |
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10.1016/j.pnucene.2018.01.002 doi (DE-627)ELV004357310 (ELSEVIER)S0149-1970(18)30010-6 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Margulis, M. verfasserin (orcid)0000-0002-7188-3301 aut The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis Blaise, P. verfasserin aut Mellier, F. verfasserin aut Gilad, E. verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 105, Seite 124-135 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:105 pages:124-135 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 105 124-135 |
| spelling |
10.1016/j.pnucene.2018.01.002 doi (DE-627)ELV004357310 (ELSEVIER)S0149-1970(18)30010-6 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Margulis, M. verfasserin (orcid)0000-0002-7188-3301 aut The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis Blaise, P. verfasserin aut Mellier, F. verfasserin aut Gilad, E. verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 105, Seite 124-135 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:105 pages:124-135 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 105 124-135 |
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10.1016/j.pnucene.2018.01.002 doi (DE-627)ELV004357310 (ELSEVIER)S0149-1970(18)30010-6 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Margulis, M. verfasserin (orcid)0000-0002-7188-3301 aut The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis Blaise, P. verfasserin aut Mellier, F. verfasserin aut Gilad, E. verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 105, Seite 124-135 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:105 pages:124-135 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 105 124-135 |
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10.1016/j.pnucene.2018.01.002 doi (DE-627)ELV004357310 (ELSEVIER)S0149-1970(18)30010-6 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Margulis, M. verfasserin (orcid)0000-0002-7188-3301 aut The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis Blaise, P. verfasserin aut Mellier, F. verfasserin aut Gilad, E. verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 105, Seite 124-135 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:105 pages:124-135 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 105 124-135 |
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10.1016/j.pnucene.2018.01.002 doi (DE-627)ELV004357310 (ELSEVIER)S0149-1970(18)30010-6 DE-627 ger DE-627 rda eng 620 DE-600 52.50 bkl Margulis, M. verfasserin (orcid)0000-0002-7188-3301 aut The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients 2018 nicht spezifiziert zzz rdacontent Computermedien c rdamedia Online-Ressource cr rdacarrier The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis Blaise, P. verfasserin aut Mellier, F. verfasserin aut Gilad, E. verfasserin aut Enthalten in Progress in nuclear energy Amsterdam [u.a.] : Elsevier Science, 1977 105, Seite 124-135 Online-Ressource (DE-627)320412032 (DE-600)2001442-9 (DE-576)251938190 0149-1970 nnns volume:105 pages:124-135 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 105 124-135 |
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Margulis, M. ddc 620 bkl 52.50 misc SNEAK-12B misc Core disruption misc Severe accidents misc LMFBR misc Sensitivity analysis misc Uncertainty analysis The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients |
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620 DE-600 52.50 bkl The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients SNEAK-12B Core disruption Severe accidents LMFBR Sensitivity analysis Uncertainty analysis |
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the path for innovative severe accident neutronics studies in zprs. part ii.2 - interpretation of sneak-12b experiment for core disruption in lmfbrs impact of nuclear data uncertainties on reactivity coefficients |
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The path for innovative severe accident neutronics studies in ZPRs. Part II.2 - Interpretation of SNEAK-12B experiment for core disruption in LMFBRs impact of nuclear data uncertainties on reactivity coefficients |
| abstract |
The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. |
| abstractGer |
The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. |
| abstract_unstemmed |
The present work details further information regarding a new benchmark to be introduced to the international community, for dealing with neutronic code validation in the frame of the analysis of severe accidents in fast reactors leading to core degradation and material relocation. This specific benchmark is based on further analysis of selected experiments performed at the Schnelle Null-Energie-Anordnung Karlsruhe (SNEAK). The SNEAK-12B core was loaded with plutonium fuel to better represent future fast systems and the experiments considered fuel relocation and redistribution of structural material. In this paper, the experimental results are analyzed by state of the art tools, Serpent-2 Monte Carlo and the ERANOS code for deterministic calculations. The paper presents a full sensitivity and uncertainty analysis based on the JEFF-3.1.1 and the associated covariance data COMAC-V01, which is performed in order to gain deeper insight into the governing phenomena related to geometrical changes of the core. A comparison of the propagated uncertainties between Serpent and ERANOS is made. The uncertainty propagation vary from code to code, and strongly disagree in most cases of axial fuel relocation. This is evident for small reactivity variation ( < 1 cent), where the difference in the propagated uncertainties obtained from the two codes is vividly visible. The analysis provide valuable information on uncertainty propagation in a system where the overall material balance is not modified, and contributes to the design of future experiments. This work is done within the frame of new core design capacities and innovative experimental programs to be implemented in Zero Power Reactors, such as the ZEPHYR project led independently by CEA. |
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| score |
7.4013395 |