Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass
To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order...
Ausführliche Beschreibung
Gespeichert in:
| Autor*in: |
Raepsaet, C. [verfasserIn] |
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| Format: |
E-Artikel |
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| Sprache: |
Englisch |
| Erschienen: |
2014transfer abstract |
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| Schlagwörter: |
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| Umfang: |
4 |
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| Übergeordnetes Werk: |
Enthalten in: Editorial Comment - Unwala, Darius J. ELSEVIER, 2013, a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics, Amsterdam [u.a.] |
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| Übergeordnetes Werk: |
volume:331 ; year:2014 ; day:15 ; month:07 ; pages:74-77 ; extent:4 |
| Links: |
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| DOI / URN: |
10.1016/j.nimb.2013.12.044 |
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| 520 | |a To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. | ||
| 520 | |a To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. | ||
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10.1016/j.nimb.2013.12.044 doi GBVA2014005000027.pica (DE-627)ELV027935760 (ELSEVIER)S0168-583X(14)00171-2 DE-627 ger DE-627 rakwb eng 530 530 DE-600 610 VZ 610 VZ 44.85 bkl Raepsaet, C. verfasserin aut Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass 2014transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. Nuclear microprobe Elsevier Nuclear glass Elsevier Helium diffusion Elsevier NRA Elsevier Peuget, S. oth Khodja, H. oth Gutierrez, G. oth Hoarau, J. oth Sauvage, T. oth Enthalten in Elsevier Unwala, Darius J. ELSEVIER Editorial Comment 2013 a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics Amsterdam [u.a.] (DE-627)ELV011304669 volume:331 year:2014 day:15 month:07 pages:74-77 extent:4 https://doi.org/10.1016/j.nimb.2013.12.044 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA GBV_ILN_21 GBV_ILN_22 GBV_ILN_24 GBV_ILN_40 GBV_ILN_62 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2007 44.85 Kardiologie Angiologie VZ AR 331 2014 15 0715 74-77 4 045F 530 |
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10.1016/j.nimb.2013.12.044 doi GBVA2014005000027.pica (DE-627)ELV027935760 (ELSEVIER)S0168-583X(14)00171-2 DE-627 ger DE-627 rakwb eng 530 530 DE-600 610 VZ 610 VZ 44.85 bkl Raepsaet, C. verfasserin aut Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass 2014transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. Nuclear microprobe Elsevier Nuclear glass Elsevier Helium diffusion Elsevier NRA Elsevier Peuget, S. oth Khodja, H. oth Gutierrez, G. oth Hoarau, J. oth Sauvage, T. oth Enthalten in Elsevier Unwala, Darius J. ELSEVIER Editorial Comment 2013 a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics Amsterdam [u.a.] (DE-627)ELV011304669 volume:331 year:2014 day:15 month:07 pages:74-77 extent:4 https://doi.org/10.1016/j.nimb.2013.12.044 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA GBV_ILN_21 GBV_ILN_22 GBV_ILN_24 GBV_ILN_40 GBV_ILN_62 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2007 44.85 Kardiologie Angiologie VZ AR 331 2014 15 0715 74-77 4 045F 530 |
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10.1016/j.nimb.2013.12.044 doi GBVA2014005000027.pica (DE-627)ELV027935760 (ELSEVIER)S0168-583X(14)00171-2 DE-627 ger DE-627 rakwb eng 530 530 DE-600 610 VZ 610 VZ 44.85 bkl Raepsaet, C. verfasserin aut Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass 2014transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. Nuclear microprobe Elsevier Nuclear glass Elsevier Helium diffusion Elsevier NRA Elsevier Peuget, S. oth Khodja, H. oth Gutierrez, G. oth Hoarau, J. oth Sauvage, T. oth Enthalten in Elsevier Unwala, Darius J. ELSEVIER Editorial Comment 2013 a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics Amsterdam [u.a.] (DE-627)ELV011304669 volume:331 year:2014 day:15 month:07 pages:74-77 extent:4 https://doi.org/10.1016/j.nimb.2013.12.044 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA GBV_ILN_21 GBV_ILN_22 GBV_ILN_24 GBV_ILN_40 GBV_ILN_62 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2007 44.85 Kardiologie Angiologie VZ AR 331 2014 15 0715 74-77 4 045F 530 |
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10.1016/j.nimb.2013.12.044 doi GBVA2014005000027.pica (DE-627)ELV027935760 (ELSEVIER)S0168-583X(14)00171-2 DE-627 ger DE-627 rakwb eng 530 530 DE-600 610 VZ 610 VZ 44.85 bkl Raepsaet, C. verfasserin aut Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass 2014transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. Nuclear microprobe Elsevier Nuclear glass Elsevier Helium diffusion Elsevier NRA Elsevier Peuget, S. oth Khodja, H. oth Gutierrez, G. oth Hoarau, J. oth Sauvage, T. oth Enthalten in Elsevier Unwala, Darius J. ELSEVIER Editorial Comment 2013 a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics Amsterdam [u.a.] (DE-627)ELV011304669 volume:331 year:2014 day:15 month:07 pages:74-77 extent:4 https://doi.org/10.1016/j.nimb.2013.12.044 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA GBV_ILN_21 GBV_ILN_22 GBV_ILN_24 GBV_ILN_40 GBV_ILN_62 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2007 44.85 Kardiologie Angiologie VZ AR 331 2014 15 0715 74-77 4 045F 530 |
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10.1016/j.nimb.2013.12.044 doi GBVA2014005000027.pica (DE-627)ELV027935760 (ELSEVIER)S0168-583X(14)00171-2 DE-627 ger DE-627 rakwb eng 530 530 DE-600 610 VZ 610 VZ 44.85 bkl Raepsaet, C. verfasserin aut Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass 2014transfer abstract 4 nicht spezifiziert zzz rdacontent nicht spezifiziert z rdamedia nicht spezifiziert zu rdacarrier To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. Nuclear microprobe Elsevier Nuclear glass Elsevier Helium diffusion Elsevier NRA Elsevier Peuget, S. oth Khodja, H. oth Gutierrez, G. oth Hoarau, J. oth Sauvage, T. oth Enthalten in Elsevier Unwala, Darius J. ELSEVIER Editorial Comment 2013 a journal on accelerators, instrumentation and techniques applied to research in nuclear and atomic physics, materials science and related fields in physics Amsterdam [u.a.] (DE-627)ELV011304669 volume:331 year:2014 day:15 month:07 pages:74-77 extent:4 https://doi.org/10.1016/j.nimb.2013.12.044 Volltext GBV_USEFLAG_U GBV_ELV SYSFLAG_U SSG-OLC-PHA GBV_ILN_21 GBV_ILN_22 GBV_ILN_24 GBV_ILN_40 GBV_ILN_62 GBV_ILN_2001 GBV_ILN_2003 GBV_ILN_2005 GBV_ILN_2007 44.85 Kardiologie Angiologie VZ AR 331 2014 15 0715 74-77 4 045F 530 |
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Development of a device for helium thermal diffusion investigations by IBA in self-irradiated nuclear glass |
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To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. |
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To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. |
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To minimize the amount of nuclear waste issuing from the nuclear power plants, the solution adopted in France consists in the reprocessing of spent fuel to isolate long lived and high level radioactive waste (minor actinides and fission products). They are incorporated into a glassy matrix in order to be placed in dedicated long-term disposal repository. The confinement of the radioelements depends strongly on the integrity of the glassy matrix which could be damaged by the radiations and the generation of helium produced by α-decays of the minor actinides. In the past few years, several studies were conducted in order to understand the behaviour of helium, especially its thermal diffusion into the glassy matrix [1–3]. However none were conducted on self-irradiated samples and a validation on radioactive glasses and in the temperature range of the repository conditions is still needed. |
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