Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage
To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integrity during interim-dry storage and subsequent transport, zirconium alloy cladding tubes were hydrogen-charged to generate 250 ppm and 500 ppm hydrogen contents, simulating spent nuclear fuel degradat...
| Main Authors: | , , |
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| Format: | Article |
| Language: | English |
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Elsevier
2017-12-01
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| Series: | Nuclear Engineering and Technology |
| Subjects: | |
| Online Access: | http://www.sciencedirect.com/science/article/pii/S1738573317300505 |
| _version_ | 1819242002954321920 |
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| author | Ki-Nam Jang Hyun-Jin Cha Kyu-Tae Kim |
| author_facet | Ki-Nam Jang Hyun-Jin Cha Kyu-Tae Kim |
| author_sort | Ki-Nam Jang |
| collection | DOAJ |
| description | To investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integrity during interim-dry storage and subsequent transport, zirconium alloy cladding tubes were hydrogen-charged to generate 250 ppm and 500 ppm hydrogen contents, simulating spent nuclear fuel degradation. The hydrogen-charged specimens were heated to four peak temperatures of 250°C, 300°C, 350°C, and 400°C, and then cooled to room temperature at cooling rates of 0.3 °C/min under three tensile hoop stresses of 80 MPa, 100 MPa, and 120 MPa. The cool-down specimens showed that high peak heat-up temperature led to lower hydrogen content and that larger tensile hoop stress generated larger radial hydride fraction and consequently lower plastic elongation. Based on these out-of-pile cladding tube test results only, it may be said that peak cladding temperature should be limited to a level < 250°C, regardless of the cladding hoop stress, to ensure cladding integrity during interim-dry storage and subsequent transport. |
| first_indexed | 2024-12-23T14:32:53Z |
| format | Article |
| id | doaj.art-182bb95c55004e59b9e7771ca0c5dd19 |
| institution | Directory Open Access Journal |
| issn | 1738-5733 |
| language | English |
| last_indexed | 2024-12-23T14:32:53Z |
| publishDate | 2017-12-01 |
| publisher | Elsevier |
| record_format | Article |
| series | Nuclear Engineering and Technology |
| spelling | doaj.art-182bb95c55004e59b9e7771ca0c5dd192022-12-21T17:43:26ZengElsevierNuclear Engineering and Technology1738-57332017-12-014981740174710.1016/j.net.2017.08.012Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storageKi-Nam JangHyun-Jin ChaKyu-Tae KimTo investigate allowable peak cladding temperature and hoop stress for maintenance of cladding integrity during interim-dry storage and subsequent transport, zirconium alloy cladding tubes were hydrogen-charged to generate 250 ppm and 500 ppm hydrogen contents, simulating spent nuclear fuel degradation. The hydrogen-charged specimens were heated to four peak temperatures of 250°C, 300°C, 350°C, and 400°C, and then cooled to room temperature at cooling rates of 0.3 °C/min under three tensile hoop stresses of 80 MPa, 100 MPa, and 120 MPa. The cool-down specimens showed that high peak heat-up temperature led to lower hydrogen content and that larger tensile hoop stress generated larger radial hydride fraction and consequently lower plastic elongation. Based on these out-of-pile cladding tube test results only, it may be said that peak cladding temperature should be limited to a level < 250°C, regardless of the cladding hoop stress, to ensure cladding integrity during interim-dry storage and subsequent transport.http://www.sciencedirect.com/science/article/pii/S1738573317300505Hydride-induced fractureHydride reorientationTerminal cool-down temperatureZirconium alloy |
| spellingShingle | Ki-Nam Jang Hyun-Jin Cha Kyu-Tae Kim Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage Nuclear Engineering and Technology Hydride-induced fracture Hydride reorientation Terminal cool-down temperature Zirconium alloy |
| title | Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage |
| title_full | Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage |
| title_fullStr | Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage |
| title_full_unstemmed | Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage |
| title_short | Allowable peak heat-up cladding temperature for spent fuel integrity during interim-dry storage |
| title_sort | allowable peak heat up cladding temperature for spent fuel integrity during interim dry storage |
| topic | Hydride-induced fracture Hydride reorientation Terminal cool-down temperature Zirconium alloy |
| url | http://www.sciencedirect.com/science/article/pii/S1738573317300505 |
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