Characterisation of neutron field in the polyethylene neutron irradiator

Rataj, Jan; Suk, Pavel; Bily, Tomas; Štefánik, Milan; Frýbort, Jan

doi:10.1016/j.apradiso.2020.109529

Cited by 4 publications

(3 citation statements)

References 14 publications

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“…Of all irradiation chambers, fast neutrons comprise no more than 20% of all neutrons travelling through the chambers. This indicates the efficiency of high-density polyethylene in moderating fast neutrons [16][17]. Figure 8 illustrate the spatial distribution of neutrons in the room with radial beam tube while Figure 9 displays the energy distribution at the end of the radial beam tube.…”

Section: Resultsmentioning

confidence: 97%

Design of Neutron Activation and Radiography Facilities Based on DD Generator

Prastowo

2023

ijp

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Design and simulation of radiation facility using deuterium-deuterium (DD) neutron generator for neutron activation analysis (NAA) and radiography have been conducted by PHITS 3.30. A cylindrical DD neutron tube (E = 2.45 MeV isotropic, 5 x 109/s) flux is surrounded by high-density polyethylene blocks which serve as the moderator. Within the moderator there are several cavities to perform neutron activation experiments. A 90 cm long beam tube is installed either radially or tangentially for radiography purposes. Monte Carlo simulations then calculate the thermal flux inside the cavities and on the end of the beam tube. The biggest thermal flux obtained in the activation chambers is about 1.95 x 109/(cm2.s) in the cavity closest to the source center. Radial beam tube delivers thermal flux of 7.86 x 103/(cm2.s), while tangential beam tube transports 1.86 x 103/(cm2.s). Although the thermal flux in the radial beam tube is higher, the fast neutron flux is also higher, about 9.60 x 103/(cm2.s). Tangential beam tube configuration can decrease fast neutron flux to only 2.00 x 102/(cm2.s). This result can serve as a preliminary study for the commisioning of radiation facilities based on compact, low-power neutron source.

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Section: Resultsmentioning

confidence: 97%

Design of Neutron Activation and Radiography Facilities Based on DD Generator

Prastowo

2023

ijp

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“…1 and 2. It is used for experiments with radionuclide neutron sources and electronic neutron generators [3]. The neutron generator was placed inside a central channel of the polyethylene box of 50 x 50 cm x 100 cm, the cadmium covered detector was placed in one of the dry experimental channels with diameter of 7 cm, the centre of the detectors was located 10.5 cm from the centre of the tube.…”

Section: Experimental Set-upmentioning

confidence: 99%

“…In case A (moderated geometry), the generator was placed inside PE block of 50 x 50 x 100 cm; the detectors were placed in dry channels with diameter of 7 cm. One detector was simulated as bare, another was covered by 1 mm thick cadmium sheet with density of 8.65 g/cm 3 .…”

Section: Fig 3 Geometry Used In Calculationsmentioning

confidence: 99%

Characterization of neutron emission during pulse mode of low output electronic neutron generator

Bily

Huml

2021

EPJ Web Conf.

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The paper deals with the characterization of the neutron output during operation the neutron generator in the pulsing mode. The characterization is performed by a cadmium covered He-3 detector. First, the adequacy of a cadmium covered He-3 detector to study the pulsed mode operation of neutron generator is assessed using Monte Carlo simulations in MCNP6 code. Second, the pulsing mode operation of the D-D P-385 Thermo Fisher Scientific neutron generator with a maximal neutron output of 7 x 106 n/s is studied. The study shows the dependence of neutron emission and pulse shapes on the frequency, duty factor, high voltage and beam current.

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