| DOI: | 10.2172/1260880
|
| 报告号: | INL/EXT--15-36169
|
| 报告题名: | AGR-1 Compact 4-1-1 Post-Irradiation Examination Results |
| 作者: | Demkowicz, Paul Andrew; Harp, Jason M.; Winston, Philip L.; Ploger, Scott A.; van Rooyen, Isabella J.
|
| 出版年: | 2016
|
| 发表日期: | 2016-02-01
|
| 总页数: | 80
|
| 国家: | 美国
|
| 语种: | 英语
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| 英文关键词: | Deconsolidation-leach-burn-leach
; Inner pyrolytic carbon
; PIE
|
| 中文主题词: | 碳
; 同位素
; 剥蚀
|
| 主题词: | CARBON
; ISOTOPES
; DEGRADATION
|
| 英文摘要: | Destructive post-irradiation examination was performed on AGR-1 fuel Compact 4-1-1, which was irradiated to a final compact-average burnup of 19.4% FIMA (fissions per initial metal atom) and a time-average, volume-average temperature of 1072°C. The analysis of this compact focused on characterizing the extent of fission product release from the particles and examining particles to determine the condition of the kernels and coating layers. The work included deconsolidation of the compact and leach-burn-leach analysis, visual inspection and gamma counting of individual particles, metallurgical preparation of selected particles, and examination of particle cross-sections with optical microscopy, electron microscopy, and elemental analysis. Deconsolidation-leach-burn-leach (DLBL) analysis revealed no particles with failed TRISO or failed SiC layers (as indicated by very low uranium inventory in all of the leach solutions). The total fractions of the predicted compact inventories of fission products Ce-144, Cs-134, Cs-137, and Sr-90 that were present in the compact outside of the SiC layers were <2Ă10-6, based on DLBL data. The Ag-110m fraction in the compact outside the SiC layers was 3.3Ă10-2, indicating appreciable release of silver through the intact coatings and subsequent retention in the OPyC layers or matrix. The Eu-154 fraction was 2.4Ă10-4, which is equivalent to the inventory in one average particle, and indicates a small but measurable level of release from the intact coatings. Gamma counting of 61 individual particles indicated no particles with anomalously low fission product retention. The average ratio of measured inventory to calculated inventory was close to a value of 1.0 for several fission product isotopes (Ce-144, Cs-134, and Cs-137), indicating good retention and reasonably good agreement with the predicted inventories. Measured-to-calculated (M/C) activity ratios for fission products Eu-154, Eu-155, Ru-106, Sb-125, and Zr-95 were significantly less than 1.0. However, as no significant release of these fission products from compacts was noted during previous analysis of the AGR-1 capsule components, the low M/C ratios are most likely an indication of a bias in the inventories predicted by physics simulations of the AGR-1 experiment. The distribution of Ag-110m M/C ratios was centered on a value of 1.02 and was fairly broad (standard deviation of 0.18, with values as high as 1.42 and as low as 0.68). Based on all data gathered to date, it is believed that silver retention in the particles was on average relatively high, but that the broad distribution in values among the particles represents significant variation in the inventory of Ag-110m generated in the particles. Ceramographic analysis of particle cross-sections revealed many of the characteristic microstructures often observed in irradiated AGR-1 particles from other fuel compacts. Palladium-rich fission product clusters were observed in the IPyC and SiC layers near the IPyC-SiC interface of three Compact 4-1-1 particle cross-sections. In spite of the presence of fission product clusters in the SiC layer, no significant corrosion or degradation of the layer was observed in any of the particles examined. |
| URL: | http://www.osti.gov/scitech/servlets/purl/1260880
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| Citation statistics: |
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| 资源类型: | 研究报告
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| 标识符: | http://119.78.100.158/handle/2HF3EXSE/42291
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| Appears in Collections: | 过去全球变化的重建
影响、适应和脆弱性
科学计划与规划
气候变化与战略
全球变化的国际研究计划
气候减缓与适应
气候变化事实与影响
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Version |
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| 1260880.pdf（10521KB） | 研究报告 | -- | 开放获取 | | View
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| Recommended Citation: | |
Demkowicz, Paul Andrew,Harp, Jason M.,Winston, Philip L.,et al. AGR-1 Compact 4-1-1 Post-Irradiation Examination Results. 2016-01-01.
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