Pub Date : 2020-12-04DOI: 10.1201/9781003070344-27
B. Sehgal, A. Wassel, D. Bugby, R. Ritzman
{"title":"Fission Product Transport during In-Vessel Progression of PWR Severe Accidents","authors":"B. Sehgal, A. Wassel, D. Bugby, R. Ritzman","doi":"10.1201/9781003070344-27","DOIUrl":"https://doi.org/10.1201/9781003070344-27","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"18 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127822866","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-53
H. M. Van Rij, V. Vonka
{"title":"The Influence of the Sensible Heat Removal on the Condensation onto Aerosols inside a Light Water Reactor Containment","authors":"H. M. Van Rij, V. Vonka","doi":"10.1201/9781003070344-53","DOIUrl":"https://doi.org/10.1201/9781003070344-53","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"51 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127584887","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-49
D. Powers, D. R. Bradley, J. Brockmann, E. R. Copus, G. Greene, S. Burson
{"title":"Validation of Core Debris/Concrete Interactions and Source Term Models","authors":"D. Powers, D. R. Bradley, J. Brockmann, E. R. Copus, G. Greene, S. Burson","doi":"10.1201/9781003070344-49","DOIUrl":"https://doi.org/10.1201/9781003070344-49","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"8 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124022672","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-42
H. Unger, M. Bürger, E. Hicken
{"title":"Ex-vessel Melt/Water Interaction","authors":"H. Unger, M. Bürger, E. Hicken","doi":"10.1201/9781003070344-42","DOIUrl":"https://doi.org/10.1201/9781003070344-42","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"41 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124106355","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-30
A. Markovina, P. Fasoli-Stella, A. Mailliat
{"title":"Review of the Major Predicted Phenomena during FP Transport and Deposition in the RCS and Containment Building under Severe Accident Conditions","authors":"A. Markovina, P. Fasoli-Stella, A. Mailliat","doi":"10.1201/9781003070344-30","DOIUrl":"https://doi.org/10.1201/9781003070344-30","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"120 11","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"132483227","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-56
J. Liljenzin, O. Lindqvist
{"title":"Influence of Minor Materials on Iodine Behavior","authors":"J. Liljenzin, O. Lindqvist","doi":"10.1201/9781003070344-56","DOIUrl":"https://doi.org/10.1201/9781003070344-56","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"799 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127123299","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-58
F. Abbey, S. A. Ramsdale
{"title":"Heat and Mass Transfer from Bubbles Rising through Pools","authors":"F. Abbey, S. A. Ramsdale","doi":"10.1201/9781003070344-58","DOIUrl":"https://doi.org/10.1201/9781003070344-58","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129777339","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 2020-12-04DOI: 10.1201/9781003070344-18
A. Strupczewski
{"title":"Fission Product Release from Fuel Elements under Stationary and Accident Conditions","authors":"A. Strupczewski","doi":"10.1201/9781003070344-18","DOIUrl":"https://doi.org/10.1201/9781003070344-18","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"21 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"121524411","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"The Chemistry of Water Reactor Fuel","authors":"P. E. Potter","doi":"10.1201/9781003070344-8","DOIUrl":"https://doi.org/10.1201/9781003070344-8","url":null,"abstract":"","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"22 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2020-12-04","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"115031270","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Pub Date : 1986-02-01DOI: 10.1201/9781003070344-66
E. Tolman, J. Broughton, R. K. McCardell, S. Langer, R. Hobbins, W. F. Domenico, P. Davis
This report establishes the basis and scope of work for the Three Mile Island Unit No. 2 (TMI-2) Accident Evaluation Program sponsored by the Department of Energy (DOE). The current understanding of the TMI-2 accident is reviewed, with emphasis on the end-state distribution of important radioisotopes and the progression of core damage leading to gross core failure and fuel migration into the lower plenum regions of the reactor vessel. Unresolved technical issues related to core damage progression and fission product behavior in hypothesized reactor accidents are identified. The role of TMI-2 accident research in addressing these unresolved issues is developed and discussed. Data needs from TMI-2 and supporting analysis requirements to interpret the data are identified that will improve our understanding of the important physical processes and parameters controlling core damage progression and the resulting fission product behavior. 48 refs.
{"title":"The TMI-2 Accident Evaluation Program","authors":"E. Tolman, J. Broughton, R. K. McCardell, S. Langer, R. Hobbins, W. F. Domenico, P. Davis","doi":"10.1201/9781003070344-66","DOIUrl":"https://doi.org/10.1201/9781003070344-66","url":null,"abstract":"This report establishes the basis and scope of work for the Three Mile Island Unit No. 2 (TMI-2) Accident Evaluation Program sponsored by the Department of Energy (DOE). The current understanding of the TMI-2 accident is reviewed, with emphasis on the end-state distribution of important radioisotopes and the progression of core damage leading to gross core failure and fuel migration into the lower plenum regions of the reactor vessel. Unresolved technical issues related to core damage progression and fission product behavior in hypothesized reactor accidents are identified. The role of TMI-2 accident research in addressing these unresolved issues is developed and discussed. Data needs from TMI-2 and supporting analysis requirements to interpret the data are identified that will improve our understanding of the important physical processes and parameters controlling core damage progression and the resulting fission product behavior. 48 refs.","PeriodicalId":130450,"journal":{"name":"Fission Product Transport Processes in Reactor Accidents","volume":"35 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1986-02-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123838056","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
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