Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

Košťál, Michal; Cvachovec, František; Rypar, Vojtěch; Juříček, Vlastimil

doi:10.1016/j.anucene.2011.10.003

Cited by 17 publications

(4 citation statements)

References 5 publications

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“…This discrepancy reflects the low resolution of stilbene detector, which does not allow differentiation of spectrum peak due to negative resonances of 16 O isotope at the energy of 2.35 MeV. A similar discrepancy can be observed in fast neutron transport in water [8]. The discrepancy in concrete is greater than those in water layer of an equivalent thickness, because the concrete has roughly six times more oxygen atoms per a hydrogen atom than the water.…”

Section: Fast Neutron Transportmentioning

confidence: 74%

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The effect of concrete shielding on neutron transport in the VVER-1000 mock-up

Košťál

Milčák

Rypar

et al. 2014

Progress in Nuclear Science and Technology

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The paper shows a comparison of measured and calculated parameters of fast and thermal neutron transport in the reactor pressure vessel mock-up and in the model of biological shielding of the VVER-1000 reactor, which are placed in the LR-0 experimental reactor. The effect of concrete shielding on the transport of thermal neutrons in the surrounding area was also investigated. Transport calculations were performed by MCNP code using CENDL 3.1 and ENDF/B VII data libraries.

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Section: Fast Neutron Transportmentioning

confidence: 74%

“…It is caused by the cross section of the steel which forms the RPV simulator. In the concrete, the opposite phenomenon is observed, similar to the transport through water [8], i.e. a hardening of the spectrum with an increasing number of higher energy neutrons.…”

Section: Fast Neutron Transportmentioning

confidence: 85%

The effect of concrete shielding on neutron transport in the VVER-1000 mock-up

Košťál

Milčák

Rypar

et al. 2014

Progress in Nuclear Science and Technology

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“…The Watt distribution of 235 U thermal neutron fission spectra was used for neutron source emission spectra definition because of the negligible differences in the emission spectra between the peripheral pin, the pin on the boundary with water gap and the Watt distribution. More details can be found in [14].…”

Section: Fast Neutron Spectra Calculationsmentioning

confidence: 99%

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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“…Considering good agreement between the models and measurement the results of dpa and gamma heating calculations seem reasonable. The measurement uncertainties can be found in [10].…”

Section: Uncertainties and Validationmentioning

confidence: 99%

Estimation of material degradation of VVER-1000 baffle

Harutyunyan¹,

Košál²,

Vandlik³

et al. 2017

EPJ Web Conf.

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Abstract. The planned lifetime of the first commercial VVER-1000 units were designed for 30 to 35 years. Most of the early VVER plants are now reaching and/or passing the 35-year mark. Service life extension for another 10 to 30 years is now under investigation. Life extension requires the evaluation of pressure vessel internals degradation under long-term irradiation. One of the possible limiting factors for the service life of VVERs is a void swelling of the Russian type titanium stabilized stainless 08Ch18N10T steel used to construct the baffle surrounding the core. This article aims to show first steps towards deeper analysis of the baffle degradation process and to demonstrate the possibilities of precise calculation and measurements on the VVER-1000 mock-up in LR-0 reactor.

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Calculation and measurement of neutron flux in the VVER-1000 mock-up on the LR-0 research reactor

Cited by 17 publications

References 5 publications

The effect of concrete shielding on neutron transport in the VVER-1000 mock-up

The effect of concrete shielding on neutron transport in the VVER-1000 mock-up

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

Estimation of material degradation of VVER-1000 baffle

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