Development methodology on determination of instant release fractions for generic safety assessment for direct disposal of spent nuclear fuel
Direct disposal of spent nuclear fuel (SNF) in deep underground repositories (hereafter “direct disposal”) is a concept that disposal canisters stored fuel assemblies dispose without reprocessing. Behavior of radionuclide release from SNF must be different from that from vitrified glass. The prese...
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| Published in | Journal of Nuclear Fuel Cycle and Environment Vol. 27; no. 2; pp. 83 - 93 |
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| Main Authors | , , |
| Format | Journal Article |
| Language | English Japanese |
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Division of Nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan
15.12.2020
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| Online Access | Get full text |
| ISSN | 1884-7579 1884-7579 |
| DOI | 10.3327/jnuce.27.2_83 |
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| Abstract | Direct disposal of spent nuclear fuel (SNF) in deep underground repositories (hereafter “direct disposal”) is a concept that disposal canisters stored fuel assemblies dispose without reprocessing. Behavior of radionuclide release from SNF must be different from that from vitrified glass. The present study established a methodology on determination of instant release fraction (IRF) of radionuclides from SNF, which is the one of the parameters on radionuclide release based on the latest safety assessment reports in other countries, especially for IRF values proportional to a fission gas release ratio (FGR). Recommended and maximum values of FGR have been estimated using the fuel performance code FEMAXI-7 after collecting FGR values on Japanese SNFs. Furthermore, recommended and maximum values of IRF for Japanese SNFs used in a pressurized water reactor (PWR) have been estimated using the presently obtained FGR values and experimentally obtained IRF values on foreign SNFs. The recommended and maximum IRF values obtained in the present study have been compared with those of the latest safety assessment reports in other countries. |
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| AbstractList | Direct disposal of spent nuclear fuel (SNF) in deep underground repositories (hereafter “direct disposal”) is a concept that disposal canisters stored fuel assemblies dispose without reprocessing. Behavior of radionuclide release from SNF must be different from that from vitrified glass. The present study established a methodology on determination of instant release fraction (IRF) of radionuclides from SNF, which is the one of the parameters on radionuclide release based on the latest safety assessment reports in other countries, especially for IRF values proportional to a fission gas release ratio (FGR). Recommended and maximum values of FGR have been estimated using the fuel performance code FEMAXI-7 after collecting FGR values on Japanese SNFs. Furthermore, recommended and maximum values of IRF for Japanese SNFs used in a pressurized water reactor (PWR) have been estimated using the presently obtained FGR values and experimentally obtained IRF values on foreign SNFs. The recommended and maximum IRF values obtained in the present study have been compared with those of the latest safety assessment reports in other countries. |
| Author | NAGATA, Masanobu AKAHORI, Kuniaki KITAMURA, Akira |
| Author_xml | – sequence: 1 fullname: AKAHORI, Kuniaki organization: Mitsubishi Materials Corporation – sequence: 1 fullname: KITAMURA, Akira organization: Japan Atomic Energy Agency – sequence: 1 fullname: NAGATA, Masanobu organization: Japan Atomic Energy Agency |
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| Cites_doi | 10.1016/0022-3115(82)90419-6 10.2113/gselements.2.6.343 |
| ContentType | Journal Article |
| Copyright | 2020 Division of Nuclear Fuel Cycle and Environment, Atomic Energy Society of Japan |
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JAEA-Data/Code 2013-014 (2013). – ident: 2 – ident: 18 – ident: 4 – ident: 12 – ident: 11 doi: 10.1016/0022-3115(82)90419-6 – ident: 10 – ident: 16 – ident: 14 – ident: 24 – ident: 9 – ident: 7 – ident: 20 – ident: 22 – ident: 17 – ident: 3 – ident: 5 – ident: 19 – ident: 1 doi: 10.2113/gselements.2.6.343 – ident: 13 – ident: 15 – ident: 6 – ident: 8 – ident: 21 – ident: 25 – ident: 23 |
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| Title | Development methodology on determination of instant release fractions for generic safety assessment for direct disposal of spent nuclear fuel |
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