| dc.contributor.author | Lianjie, Wang | |
| dc.contributor.author | Di, Lu | |
| dc.contributor.author | Wenbo, Zhao | |
| dc.date.accessioned | 2019-03-17T09:41:17Z | |
| dc.date.available | 2019-03-17T09:41:17Z | |
| dc.date.copyright | 1/24/2019 12:00:00 AM | |
| dc.date.issued | 2019 | |
| dc.identifier.issn | 2332-8983 | |
| dc.identifier.other | ners_005_01_011010.pdf | |
| dc.identifier.uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4255618 | |
| dc.description.abstract | Transient performance of China supercritical water-cooled reactor (SCWR) with the rated electric power of 1000 MWel (CSR1000) core during some typical transients, such as control rod (CR) ejection and uncontrolled CR withdrawal, is analyzed and evaluated with the coupled three-dimensional neutronics and thermal-hydraulics SCWR transient analysis code. The 3D transient analysis shows that the maximum cladding surface temperature (MCST) retains lower than safety criteria 1260 °C during the process of CR ejection accident, and the MCST retains lower than safety criteria 850 °C during the process of uncontrolled CR withdrawal transient. The safety of CSR1000 core can be ensured during the typical transients under the salient fuel temperature and water density reactivity feedback and the essential reactor protection system. | |
| dc.publisher | The American Society of Mechanical Engineers (ASME) | |
| dc.title | Coupled Three-Dimensional Neutronics and Thermal-Hydraulics Analysis for SCWR Core Typical Transients | |
| dc.type | Journal Paper | |
| dc.journal.volume | 5 | |
| dc.journal.issue | 1 | |
| dc.journal.title | Journal of Nuclear Engineering and Radiation Science | |
| dc.identifier.doi | 10.1115/1.4041693 | |
| dc.journal.fristpage | 11010 | |
| dc.journal.lastpage | 011010-6 | |
| dc.tree | Journal of Nuclear Engineering and Radiation Science:;2019:;volume( 005 ):;issue: 001 | |
| dc.contenttype | Fulltext | |
