Neutron and photon transport in Fe with the employment of TENDL 2009, CENDL 3.1, JENDL 4 and JENDL 4 evolution from JENDL 3.3 in case of Fe

Košťál, Michal; Cvachovec, František; Cvachovec, Jiří; Ošmera, B.; Hansen, W.

doi:10.1016/j.nucengdes.2012.04.007

Cited by 3 publications

(1 citation statement)

References 4 publications

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“…The calculation/experiment discrepancy on the outer RPV surface is significantly higher in the case of JENDL 4 than in JENDL 3.3 and other libraries. Similar results concerning calculation of neutrons transport through iron using JENDL 3.3 and JENDL 4 were reported in [16].…”

Section: Discussionsupporting

confidence: 86%

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

Košťál

Milčák

Cvachovec

et al. 2016

EPJ Web of Conferences

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Abstract.A set of benchmark experiments was carried out in the full scale VVER-1000 mock-up on the reactor LR-0 in order to validate neutron transport calculation methodologies and to perform the optimization of the shape and locations of neutron flux operation monitors channels inside the shielding of the new VVER-1000 type reactors. Compared with previous experiments on the VVER-1000 mock-up on the reactor LR-0, the fast neutron spectra were measured in the extended neutron energy interval (0.1-10 MeV) and new calculations were carried out with the MCNPX code using various nuclear data libraries (ENDF/B VII.0, JEFF 3.1, JENDL 3.3, JENDL 4, ROSFOND 2009, and CENDL 3.1). Measurements and calculations were carried out at different points in the mock-up. The calculation and experimental data are compared.

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Section: Discussionsupporting

confidence: 86%

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

Košťál

Milčák

Cvachovec

et al. 2016

EPJ Web of Conferences

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Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor

Košťál

Cvachovec

Jánský

et al. 2016

Annals of Nuclear Energy

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The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

Juříček

Košťál

Losa

et al. 2021

Journal of Nuclear Engineering and Radiation Science

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The paper summarizes the issue of the validation of the silicon-filtered neutron beam transport in the structural materials important for nuclear technology. Iron, which is the most common material in the reactor technology was tested. The silicon filtered beam itself is a very interesting tool, because some significant peaks occur in the spectrum, helping to study the deep neutron transport in the steel. The character of spectrum is reflecting the silicon cross section in region 1 - 8 MeV. Because it has got a fine character, the peaks in neutron spectrum are occurring in the positions of the cross section depressions. Based on the agreement between calculated and measured attenuation in groups located within the neutron flux peaks one can reveal possible problems in neutron transport description. These results constitute a good addition to integral experiments characterizing the neutron transport in steel using 252Cf(s.f) and 235U(nth;fiss) which both have got a smooth spectrum.

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Neutron and photon transport in Fe with the employment of TENDL 2009, CENDL 3.1, JENDL 4 and JENDL 4 evolution from JENDL 3.3 in case of Fe

Cited by 3 publications

References 4 publications

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

Fast Neutron Transport in the Biological Shielding Model and Other Regions of the VVER-1000 Mock-Up on the LR-0 Research Reactor

Neutron deep penetration through reactor pressure vessel and biological concrete shield of VVER-1000 Mock-Up in LR-0 reactor

The Application of Silicon-Filtered Beam in the Validation of Iron Cross Sections by Deep Penetration Experiments

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