Measurement of various monitors reaction rate in a special core at LR-0 reactor

Košťál, Michal; Schulc, Martin; Šimon, Jan; Burianová, Nicola; Harutyunyan, Davit; Losa, Evžen; Rypar, Vojtěch

doi:10.1016/j.anucene.2017.10.036

Cited by 22 publications

(4 citation statements)

References 27 publications

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“…After the irradiation in the reactor core, the activity of irradiated activation detectors was measured using a welldefined HPGe coaxial vertical detector (Ortec GEM35). The HPGe detector efficiency was calculated using MCNP6 code in previous work, see [4] . The precise computational model for the detector was compiled using experimentally determined dimensions by a special radiogram of the crystal REF, and precisely measured dead layer.…”

Section: Hpge Detector Measurement and Reaction Rate Determinationmentioning

confidence: 99%

Specially developed LR-0 reactor graphite environment for gen IV reactor support and cross-section measurement

Peltan,

Vilimova,

Czakoj

et al. 2023

EPJ Web Conf.

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This paper is focused on the development of the experimental environment connected to reactor graphite. Regarding its very good neutronic and mechanical properties, graphite will be very important in some new reactor designs, such as high-temperature or molten salt SMR reactors. These new reactor concepts require a new experimental environment as support for further research. In the laboratories of the Research Centre Řež and at the LR-0 reactor, the new experimentally validated graphite environment was created. This large graphite insertion is the largest graphite mono-block, which is possible to assemble at the LR-0 reactor. Sets of experiments for measuring reaction rates of different activation detectors for neutron field mapping were performed. This approach was used for thermal and epithermal region descriptions. For the fast neutron spectrum evaluation, the stilbene scintillation detector was used. All parameters, such as criticality height of moderator level, neutron spectrum, and other parameters for all experiments, were performed using Monte Carlo neutronic codes Serpent and MCNP. The obtained results were finally compared to the measurement of neutron leakage spectra from the graphite cube and graphite cylinder. These specially developed graphite-shaped neutron fields, reactor insertions, and external cube and cylinder with Cf neutron source can be used in the future for validation of not only materials used in SMR reactors but for arbitrary cross-section verification.

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Section: Hpge Detector Measurement and Reaction Rate Determinationmentioning

confidence: 99%

Specially developed LR-0 reactor graphite environment for gen IV reactor support and cross-section measurement

Peltan,

Vilimova,

Czakoj

et al. 2023

EPJ Web Conf.

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“…The measurement was carried out using a well-characterized HPGe spectrometric system in the Research Centre Rez (see Kostal et al, 2018b). To minimize geometrical uncertainty in the measurements of irradiated samples, thin foils, namely Mg, Fe, 54 Fe, Mo and Ni monitors, were fixed in the plastic EG-3 holder (special plastic holder, for more details, see Fig.…”

Section: Gamma Spectrometrymentioning

confidence: 99%

“…The actual neutron flux in the reference volume is then obtained simply by calculating neutron flux multiplied by the scaling factor. This approach is possible as the neutron field used in the defined position of the monitors is the benchmark reference neutron field (Kostal et al, 2020), where the mathematical models used for the flux calculations were validated within study of the criticality (Kostal et al, 2016a), flux distribution (Kostal et al, 2018b), fission source distribution (Kostal et al, 2016b, and neutron spectrum (Kostal et al, 2015).…”

Section: Spectrum Averaged Cross Sectionsmentioning

confidence: 99%

“…It was placed in a glass vial to prevent a leak of 14 C during irradiation and to minimize the distortion of the neutron field around it. All activation detectors in this arrangement were placed into the central position of the holder (see Kostal et al, 2018b). This central position was surrounded by monitoring Au, Ta, and Ni foils.…”

Section: Evaluation Of Small Foils In Reference Volumementioning

confidence: 99%

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Special Issue: Research Center Řež: Nuclear-Engineering Activities in 2020

Košťál¹,

Schulc²

2021

Journal of Nuclear Engineering and Radiation Science

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This special issue is dedicated primarily to research performed in the Research Centre Rež (CVR, Centrum výzkumu Rež Fig. 1) during the Research for SUSEN (R4S) project, which is the follow-up of the (SUSEN) project, that was successfully completed at the end of 2020. Research Centre Rež is a research organization founded in 2002. It is a member of the UJV Group, and it is focused on the pre-commercial research in power-generation technologies, predominantly, but not exclusively, in the nuclear field. The R4S project comprised many topics, including the research and development of new technologies for current and future generations of nuclear reactor systems and nuclear fusion reactors. It was carried out within the CVR, in close partnership with the University of West Bohemia, and was funded by the Ministry of Education, Youth and Sports of the Czech Republic.

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