Preliminary Results of Neutron Transport in Blanket Module by MCNP with Profile Analysis Using Imaging Plate

Ogino, Yuka; Mukai, Keisuke; Yagi, Juro; Konishi, Satoshi

doi:10.1080/15361055.2019.1611343

Cited by 6 publications

(2 citation statements)

References 11 publications

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“…The use of the compact source allows a neutron irradiation test in a flexible arrangement of source/target geometry without expensive facilities, such as fission research reactors and accelerators. As its neutron yield is significantly low compared with accelerator-based neutron sources, detectors with ultra-high sensitivity are required [11,12]. One direct method for measuring bred tritium is to count β-rays of irradiated Li 2 CO 3 diagnostic pellets using a liquid scintillation counter (LSC), which evaluates TPR with uncertainties of 4%-10% at the 1σ level [4][5][6][13][14][15].…”

Section: Introductionmentioning

confidence: 99%

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

et al. 2021

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We report a neutronics study of a blanket mock-up using a discharge-type compact fusion neutron source. Deuterium-deuterium fusion neutrons were irradiated to the mock-ups composed of tritium breeder and neutron reflector/moderator. The tritium production rate (TPR) per source neutron was measured by a single-crystal diamond detector with a 6 Li-enriched lithium fluoride film convertor after the calibration process. Despite the low neutron yield, energetic alpha and triton particles via 6 Li(n, t)α neutron capture as well as 12 C via elastic scattering were successfully detected by the SDD with high signal to noise ratios. The TPRs were experimentally evaluated with errors of 8.4%-8.5% at the 1σ level at the positions with high thermal neutron fluxes where the errors were dominantly introduced by uncertainties in the monitoring of the neutron production rate. The calculated to experimental (C/E) values of TPR were evaluated to be 0.91-1.27 (FENDL-2.1) and 0.94-1.28 (FENDL-3.1). As the neutron source can generate 14 MeV neutrons using a mixed gas of deuterium and tritium, this approach provides more opportunities for blanket neutronics experiments.

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Section: Introductionmentioning

confidence: 99%

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

et al. 2021

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“…An evaluation is carried out through a read-out process which takes a few decades of minutes. NIP has a high spatial resolution (<200 m) and a wide dynamic range (1:10 5 ) [9], which is sensitive enough to detect neutrons from a compact DD fusion neutron source, with a linearity between neutron fluence and photo-stimulated luminescence (PSL) [10], [11]. Li2O and Li2TiO3, ceramic breeder materials for solid blanket system [12], were irradiated on the NIP to evaluate the amount of the bred tritium in this study.…”

Section: Introductionmentioning

confidence: 99%

2-D Evaluation of Bred Tritium Using Neutron Imaging Plate

Mukai

Ogino

Yagi

et al. 2020

IEEE Trans. Plasma Sci.

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Tritium breeding performance of a fusion blanket is a key parameter for the self-sufficient fueling of a fusion reactor and thus planned to validate the performance in a neutronics experiment. Measuring the two-dimensional (2D) distribution of bred tritium is challenging via conventional methods such as -ray counting from an irradiated lithium sample by a liquid scintillation counter and a single-crystal diamond detector with a thin 6 LiF film because they are point detectors which require many measurements. In present study, 2D distribution of the low quantity produced tritium was evaluated with a neutron imaging plate with a Gd convertor by estimating the loss of neutrons via a capture reaction by Li. Deuterium-deuterium fusion neutrons were generated using a compact fusion device at an average neutron production rate of 1.5×10 5 n/s by applying high voltages. A neutron image with "shadows" projected by thermal neutron capture reactions of 6 Li(n,) and 10 B(n,) was successfully obtained. The experimentally evaluated values were confirmed to be consistent with the total number of capture reactions calculated using a neutron transport code. The results suggest that the approach could be a facile method for two-dimensional evaluation of bred tritium.

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Simulations for practical measurement methods of spatial neutron distribution inside blanket mock-up irradiated with DT neutrons

Ogino

Mukai

Yagi

et al. 2021

Fusion Engineering and Design

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Preliminary Results of Neutron Transport in Blanket Module by MCNP with Profile Analysis Using Imaging Plate

Cited by 6 publications

References 11 publications

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

Evaluation of tritium production rate in a blanket mock-up using a compact fusion neutron source

2-D Evaluation of Bred Tritium Using Neutron Imaging Plate

Simulations for practical measurement methods of spatial neutron distribution inside blanket mock-up irradiated with DT neutrons

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