A fission ionization detector for neutron flux measurements at a spallation source

Wender, S. A.; Balestrini, S.J.; Brown, Ashton; Haight, R. C.; Laymon, C. M.; Lee, T.M.; Lisowski, P.W.; McCorkle, W.H.; Nelson, R. O.; Parker, W.; Hill, N. W.

doi:10.1016/0168-9002(93)91102-s

Cited by 145 publications

(48 citation statements)

References 4 publications

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“…The entire test device is defined as the FC region, and the deposit energy in a sensitive volume (0.1 × 0.1 × 0.5 μm 3 ) embedded in the silicon substrate is tallied. The incident neutron spectrum is assumed to be the same as that of the Weapons Neutron Research Facility (WNR) neu- 6) shown in Fig. 8, which is similar to a typical terrestrial neutron spectrum observed at the ground level and is widely used for accelerated tests of soft errors.…”

Section: Resultsmentioning

confidence: 99%

Implementation of a Forced Collision Method in the Estimation of Deposit Energy Distribution with the PHITS Code

Abe

Watanabe

Niita

et al. 2011

Progress in Nuclear Science and Technology

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To improve the computational efficiency of the deposit energy calculation in a very small volume due to nuclear reactions, we have attempted to implement a forced collision method in the deposit energy distribution tally of the PHITS (Particle and Heavy Ion Transport code System). The local deposit energy distribution by 100-MeV neutrons penetrating a cubic silicon cell with μm size was calculated by the modified PHITS code. It was found that the computational efficiency was improved in inverse proportion to the cell size. In the case of a 1-μm silicon cell, the forced collision method brought improvement to the computational efficiency by a factor of about 15. This indicates that the forced collision method is effective to estimate the local deposit energy distribution due to nuclear reactions in a microscopic volume.

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Section: Resultsmentioning

confidence: 99%

Implementation of a Forced Collision Method in the Estimation of Deposit Energy Distribution with the PHITS Code

Abe

Watanabe

Niita

et al. 2011

Progress in Nuclear Science and Technology

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“…The beam size was adjusted to 36 mm in diameter. A fission ionization chamber 4) was set to know the incident-neutron flux. The TOF spectrum of each NE213 detector and each spectrum of charge amounts of the area of a pulse delivered by the photomultiplier connected with the NE213 scintillator were measured.…”

Section: Methodsmentioning

confidence: 99%

Measurements of Neutron-production Double-differential Cross-sections at 100 MeV Neutron-Incidence on Fe

Kajimoto

Moriguchi

Nakamura

et al. 2011

Progress in Nuclear Science and Technology

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The neutron-induced neutron-production double-differential cross-sections at 100 MeV by bombarding a Fe sample with continuous energy neutron were measured. A fission ionization chamber was set to take the incident-neutron flux. Six NE213 liquid scintillators, 12.7 cm thick and 12.7 cm in diameter, were placed at 15 , 30 , 60 , 90 , 120 and 150 to detect neutrons emitted from a sample. Incident energies of neutrons were obtained by the time of flight (TOF) method. The distance from the spallation target to an NE213 scintillator was applied as the flight length of incident neutrons. The energy spectra of emitted neutrons were derived from unfolding their deposition-energy spectra with the response functions of the detectors. The response functions were also measured with the spallation neutrons above neutron energy of 20 MeV. In the unfolding process, neutron-induced neutron-production double-differential crosssections were approximated by the moving source model. The experimental results were compared with calculations of the PHITS code using the JENDL-HE file.

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“…During the experimental runs, 1.2 × 10 10 micropulses produced about 1.2 × 10 12 neutrons of energies from 1 to 100 MeV on target to be used in the cross-section analysis. The neutron flux on target was measured with an in-beam fission ionization chamber with 235 U and 238 U foils [14] located about two meters upstream from the center of the GEANIE array.…”

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confidence: 99%

Neutron-inducedγ-ray production cross sections for the first excited-state transitions in20Ne and22Ne

et al. 2012

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A fission ionization detector for neutron flux measurements at a spallation source

Cited by 145 publications

References 4 publications

Implementation of a Forced Collision Method in the Estimation of Deposit Energy Distribution with the PHITS Code

Implementation of a Forced Collision Method in the Estimation of Deposit Energy Distribution with the PHITS Code

Measurements of Neutron-production Double-differential Cross-sections at 100 MeV Neutron-Incidence on Fe

Neutron-inducedγ-ray production cross sections for the first excited-state transitions in20Ne and22Ne

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