On the issue of substantiation of test modes for ampoule experimental device in research reactor
The relevance of the research is caused by complementation of the information on severe accident of fast neutron power reactor in the result of computational-experimental researches. The main aim of the study is to detect thermal state of steel capsule in ampoule experimental device, designed for ge...
| Main Authors: | , , |
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| Format: | Article |
| Language: | Russian |
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Tomsk Polytechnic University
2017-11-01
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| Series: | Известия Томского политехнического университета: Инжиниринг георесурсов |
| Subjects: | |
| Online Access: | http://izvestiya.tpu.ru/archive/article/view/1903 |
| Summary: | The relevance of the research is caused by complementation of the information on severe accident of fast neutron power reactor in the result of computational-experimental researches. The main aim of the study is to detect thermal state of steel capsule in ampoule experimental device, designed for getting material melt of fast power reactor core in the conditions modeling reactor severe accident. Research methods: methods of computational modeling of neutron processes using MCNP5 specialized codes based on Monte-Carlo method, as well as the method of system finite-difference elemental analysis, implemented on ANSYS 14.0. computational software system. Results. The authors have carried out neutron-physical and thermal calculations of an ampoule irradiation device designed for investigating severe accidents of fast energy reactors (this device, in which the material of the reactor core melts, is made of materials which melting points are lower than the temperature of the resulting melt of the corium). As a result of neutronic calculations the coupling coefficient between the in-core fuel assemblies energy release in the irradiation device and ampoule energy release in the core Pulse graphite reactor was defined. From the results of the thermophysical calculation it follows that during reactor tests in the selected reactor operation mode, the maximum fuel temperature at the center of the core level is 3000 K, at the fuel element cladding is 2500 K, for the tan talum glass is 806 K, for the steel capsule is 693 K. With such temperature values, the design of the experimental device will retain its in tegrity and thereby the safety of the experiment on obtaining the full-scale corium will be achieved. |
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| ISSN: | 2500-1019 2413-1830 |