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Determination of critical assembly absolute power using post-irradiation activation measurement of week-lived fission products
M. Košťál, M. Švadlenková, J. Milčák, V. Rypar, M. Koleška,
Language English Country England, Great Britain
Document type Journal Article, Research Support, Non-U.S. Gov't
- MeSH
- Nuclear Reactors instrumentation MeSH
- Monte Carlo Method MeSH
- Half-Life MeSH
- Radioisotopes chemistry MeSH
- Spectrometry, Gamma MeSH
- Publication type
- Journal Article MeSH
- Research Support, Non-U.S. Gov't MeSH
The work presents a detailed comparison of calculated and experimentally determined net peak areas of longer-living fission products after 100 h irradiation on a reactor with power of ~630 W and several days cooling. Specifically the nuclides studied are (140)Ba, (103)Ru, (131)I, (141)Ce, (95)Zr. The good agreement between the calculated and measured net peak areas, which is better than in determination using short lived (92)Sr, is reported. The experiment was conducted on the VVER-1000 mock-up installed on the LR-0 reactor. The Monte Carlo approach has been used for calculations. The influence of different data libraries on results of calculation is discussed as well.
References provided by Crossref.org
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- $a The work presents a detailed comparison of calculated and experimentally determined net peak areas of longer-living fission products after 100 h irradiation on a reactor with power of ~630 W and several days cooling. Specifically the nuclides studied are (140)Ba, (103)Ru, (131)I, (141)Ce, (95)Zr. The good agreement between the calculated and measured net peak areas, which is better than in determination using short lived (92)Sr, is reported. The experiment was conducted on the VVER-1000 mock-up installed on the LR-0 reactor. The Monte Carlo approach has been used for calculations. The influence of different data libraries on results of calculation is discussed as well.
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