Monte Carlo uncertainty analyses for integral beryllium experiments

Fischer, U.; Perel, R.L.; Tsige‐Tamirat, H.

doi:10.1016/s0920-3796(00)00232-5

Cited by 9 publications

(3 citation statements)

References 13 publications

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“…Beryllium is the most favored neutron multiplier candidate for solid breeder blankets of future fusion power reactors [24] . A beryllium spherical shell experiment with different thicknesses was conducted at the intense 14 MeV neutron source facility OKTAVIAN.…”

Section: Beryllium (Oktavian)mentioning

confidence: 99%

Integral Data Benchmark of HENDL2.0/MG Compared with Neutronics Shielding Experiments

Jiang¹,

Xu²,

Zheng³

et al. 2009

Plasma Sci. Technol.

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HENDL2.0, the latest version of the hybrid evaluated nuclear data library, was developed based upon some evaluated data from FENDL2.1 and ENDF/B-VII. To qualify and validate the working library, an integral test for the neutron production data of HENDL2.0 was performed with a series of existing spherical shell benchmark experiments (such as V, Be, Fe, Pb, Cr, Mn, Cu, Al, Si, Co, Zr, Nb, Mo, W and Ti). These experiments were simulated numerically using HENDL2.0/MG and a home-developed code VisualBUS. Calculations were conducted with both FENDL2.1/MG and FENDL2.1/MC, which are based on a continuous-energy Monte Carlo Code MCNP/4C. By comparison and analysis of the neutron leakage spectra and the integral test, benchmark results of neutron production data are presented in this paper.

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Section: Beryllium (Oktavian)mentioning

confidence: 99%

Integral Data Benchmark of HENDL2.0/MG Compared with Neutronics Shielding Experiments

Jiang¹,

Xu²,

Zheng³

et al. 2009

Plasma Sci. Technol.

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“…An experimental validation of TBR with spectral neutron flux as well as neutron transport calculations is vital to guarantee the self-sufficiency. This is because simulation errors can be introduced by uncertainties in the nuclear data, a discrepancy in the simulated and the actual geometries, and an unexpected neutron absorption by impurities in blanket materials [1]. Therefore, it is planned to perform a neutronics experiment with a blanket mock-up initially with a cylindrical discharge-type deuterium-deuterium (DD) fusion device and later with a DT neutron source.…”

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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“…However, it should be emphasized that an experimental examination of tritium breeding performance with spectral neutron fluxes is vital. This is because errors can be caused by uncertainties in the nuclear data, a discrepancy in the simulated and the actual geometries, and an unexpected neutron absorption by impurities in the blanket materials [1]- [4]. Therefore, it is planned to perform a neutronics experiment with a blanket mock-up initially with a cylindrical discharge-type deuterium-deuterium (DD) fusion device [5], [6], and later with a DT neutron source.…”

Section: Introductionmentioning

confidence: 99%

Preparation for a neutronics experiment using a discharge fusion device and an imaging plate neutron detector

Mukai

Konishi

2019

Fusion Engineering and Design

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Tritium breeding ratio (TBR) is one of the most important parameters determining the tritium self-sufficiency of a deuterium-tritium fusion reactor. A neutronics experiment is planned to measure the spectral neutron fluences two-dimensionally (2D) using a discharge-type compact fusion neutron source and a neutron imaging plate (NIP), respectively. We report a calibration method for the NIP and optimization of the discharge condition to enhance the neutron production rate. A linear relationship between the neutron fluence in the NIP and photostimulated luminescence (PSL) per area was obtained in the range of the neutron fluence from 10 3 to 10 7 n/cm 2 . A neutron production rate higher than 10 7 n/s was successfully achieved by the optimized discharge condition. It is shown that a quantitative 2D measurement by the NIP is feasible using the linear relationship and a correlation coefficient on the energy spectrum.

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Monte Carlo uncertainty analyses for integral beryllium experiments

Cited by 9 publications

References 13 publications

Integral Data Benchmark of HENDL2.0/MG Compared with Neutronics Shielding Experiments

Integral Data Benchmark of HENDL2.0/MG Compared with Neutronics Shielding Experiments

2-D Evaluation of Bred Tritium Using Neutron Imaging Plate

Preparation for a neutronics experiment using a discharge fusion device and an imaging plate neutron detector

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