A practical method for measuring the boron equivalent of graphite impurity

Bolewski, Andrzej; Ciechanowski, M.; Dydejczyk, A.; Kreft, A.

doi:10.1016/j.nimb.2005.03.002

Cited by 8 publications

(4 citation statements)

References 11 publications

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“…The graphite insertion used in these experiments has a density of 1.72 ± 0.02 g/cm 3 , a concentration of impurities below 0.2 ppm of boron equivalent. These properties meet the nuclear graphite limits [2] .…”

Section: A Reactor Core Arrangementmentioning

confidence: 64%

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: A Reactor Core Arrangementmentioning

confidence: 64%

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 height of each graphite block is 60 cm with a hexagonal key (flat-to-flat) dimension of 21.65 cm. The graphite insertion used in these experiments has a density of 1.72 ± 0.02 g/cm 3 and a concentration of impurities below 0.2 ppm of boron equivalent and thus meets the nuclear graphite limits (Bolewski et al, 2005). The central position of the graphite cylinder has been replaced by a unique activation holder made of pure aluminium, which is used to insert the activation foils fixed in the exact place of the holder.…”

Section: Experiments Core Arrangementmentioning

confidence: 99%

Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor

Peltan

Vilimova²,

Czakoj³

et al. 2023

Annals of Nuclear Energy

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“…Because of outstanding properties such as low neutron absorption cross-section, good moderating properties, chemical inertness, capacity to withstand very high temperatures, high thermal and electrical conductivity, graphite is largely used as a moderator, reflector, and structural material in nuclear reactors (1,2). Graphite is also the base material for the preparation of mixed carbide fuels (e.g., (U, Pu)C) for the fast breeder reactors (FBR) and also has widespread industrial applications (e.g., as electrodes, crucibles, high-resistance engineering parts in the aerospace technology) (3)(4)(5)(6)(7)(8)(9). For such applications, high purity graphite is essential because the outstanding properties, in particular, the nuclear properties of graphite are strongly influenced by the presence of impurities even at low concentrations.…”

Section: Introductionmentioning

confidence: 99%

Development of Oxidative Pyrolysis Method for the Rapid Determination of Boron in Graphite Powders by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES)

Krishna¹

2014

At.Spectrosc.

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A practical method for measuring the boron equivalent of graphite impurity

Cited by 8 publications

References 11 publications

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

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

Characterisation of neutron field in large graphite insertion in special core of the LR-0 reactor

Development of Oxidative Pyrolysis Method for the Rapid Determination of Boron in Graphite Powders by Inductively Coupled Plasma Optical Emission Spectrometry (ICP-OES)

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