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Journal Articles

Development of a high-efficiency proton recoil telescope for D-T neutron fluence measurement

Tanimura, Yoshihiko; Yoshizawa, Michio

Radiation Protection Dosimetry, 180(1-4), p.417 - 421, 2018/08

BB2016-1356.pdf:0.59MB

 Times Cited Count:0 Percentile:0.01(Environmental Sciences)

A high efficiency proton recoil telescope (PRT), which consists of a radiator, a $$Delta$$E detector and an E detector, was developed to determine the neutron fluence in the 14.8 MeV mono-energetic neutron field at the FRS. A 2 mm thick plastic scintillation detector was employed as the radiator to increase the detection efficiency and compensate the energy loss of the recoil proton in the radiator. A thin and a thick silicon detectors with 150 $$mu$$m and 3 mm thick sensitive layers were employed as the $$Delta$$E and E detectors, respectively. The detection efficiency was evaluated by the neutron measurements in the 14.8 MeV field for the distances from the radiator to E detector of 50 mm, 100 mm and 150 mm. The detection efficiency increases up to 3.7 $$times$$ 10$$^{-3}$$ with the decrease in the distance, which is roughly a few orders of magnitude greater than those of common PRTs. These detection efficiencies are high enough to determine the neutron fluence at the 14.8 MeV field within a few hours.

Journal Articles

Current status of neutron calibration field of JAERI/FRS

Yoshizawa, Michio

Hokeikyo Nyusu, (29), p.2 - 5, 2002/05

no abstracts in English

Journal Articles

A Monte Carlo program for estimating characteristics of neutron calibration fields using a Pelletron accelerator

Yoshizawa, Michio; Saegusa, Jun; Yoshida, Makoto; Sugita, Takeshi*

Proceedings of 10th International Congress of the International Radiation Protection Association (IRPA-10) (CD-ROM), 4 Pages, 2000/05

no abstracts in English

JAEA Reports

Evaluation of influence of intermediate and fast neutrons mixed in a thermal neutron calibration field; Evaluation by using simulation

J.R.Dumais*; Yoshizawa, Michio; Yamaguchi, Yasuhiro

JAERI-Tech 97-033, 35 Pages, 1997/07

JAERI-Tech-97-033.pdf:1.43MB

no abstracts in English

Oral presentation

Development of a deuterium oxide-moderated $$^{241}$$Am-Li neutron field to simulate spent nuclear fuel shipping cask spectra

Hoshi, Katsuya; Yoshida, Tadayoshi; Tsujimura, Norio; Okada, Kazuhiko

no journal, , 

no abstracts in English

Oral presentation

Study on the evaluation of energy spectra of a deuterium oxide-moderated $$^{241}$$Am-Li neutron field

Hoshi, Katsuya; Nishino, Sho; Yoshida, Tadayoshi; Tsujimura, Norio; Okada, Kazuhiko

no journal, , 

no abstracts in English

Oral presentation

Current issues in radiation protection in Nuclear Fuel Cycle Engineering Laboratories; Next personal dosimeter and eye lens dosimetry

Uchida, Masahiro; Maeda, Tsuyoshi; Takimoto, Misaki; Takada, Chie; Tsujimura, Norio

no journal, , 

no abstracts in English

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