Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS EventsSource: Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002::page 20905Author:Petkov, Gueorgui I.
DOI: 10.1115/1.4039000Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future.
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| contributor author | Petkov, Gueorgui I. | |
| date accessioned | 2019-02-28T11:05:37Z | |
| date available | 2019-02-28T11:05:37Z | |
| date copyright | 3/5/2018 12:00:00 AM | |
| date issued | 2018 | |
| identifier issn | 2332-8983 | |
| identifier other | ners_004_02_020905.pdf | |
| identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4252596 | |
| description abstract | Analysis of the Core Physical Characteristics of China Experimental Fast Reactor With MCNP;The whole core model of China experimental fast reactor (CEFR) is established according to the parameters of China experimental fast reactor, which are given by technical publication from the International Atomic Energy Agency (IAEA-TECDOC-1531), and the physical parameters of CEFR are simulated with the Monte Carlo N-particle code (MCNP4a). The calculation results are compared with the data contained in the safety analysis report of CEFR. The calculation results are consistent with the design values, which successfully demonstrate the acceptable fidelity of the MCNP model. The MCNP model will be further refined and applied for nuclear safety review of the CEFR in the future. | |
| publisher | The American Society of Mechanical Engineers (ASME) | |
| title | Enhancing the Plant's Capability for Design Basis and Design Extension Conditions Based on Time-Dependent Context Evaluation of Human Performance in ATWS Events | |
| type | Journal Paper | |
| journal volume | 4 | |
| journal issue | 2 | |
| journal title | Journal of Nuclear Engineering and Radiation Science | |
| identifier doi | 10.1115/1.4039000 | |
| journal fristpage | 20905 | |
| journal lastpage | 020905-11 | |
| tree | Journal of Nuclear Engineering and Radiation Science:;2018:;volume( 004 ):;issue: 002 | |
| contenttype | Fulltext |