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Journal Articles

Present status of the FRS/JAEA with newly established accredited JIS testing laboratory

Yoshitomi, Hiroshi

FBNews, (557), p.1 - 5, 2023/05

no abstracts in English

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.

JAEA Reports

Characteristics of thermal neutron calibration fields using a graphite pile

Uchida, Yoshiaki*; Saegusa, Jun; Kajimoto, Yoichi; Tanimura, Yoshihiko; Shimizu, Shigeru; Yoshizawa, Michio

JAERI-Tech 2005-012, 31 Pages, 2005/03

JAERI-Tech-2005-012.pdf:4.58MB

no abstracts in English

Journal Articles

A Van de Graaff accelerator at facility of radiation standards

Yamamoto, Hideaki

Kasokuki, 1(3), 294 Pages, 2004/12

no abstracts in English

Journal Articles

Recalibration test of dump tank at NUCEF

Ono, Akio*

Kaku Busshitsu Kanri Senta Nyusu, 33(9), p.12 - 15, 2004/09

no abstracts in English

Journal Articles

Relation between neutron dosemeter readings and calibration fields for various workplace spectra

Saegusa, Jun; Tanimura, Yoshihiko; Yoshizawa, Michio

Proceedings of 11th International Congress of the International Radiation Protection Association (IRPA-11) (CD-ROM), 8 Pages, 2004/05

Relationships between dosemeter readings and the true dose equivalents at various workplaces were analyzed. From the analysis, it was shown that depending on the types of dosemeters, there exist a suitable calibration field, and the field differs by the difference of response characteristics of dosemeters. For the precise estimation of dose equivalent, it is important that measurement is carried out under the careful considerations of the difference between neutron spectrum at workplace and at calibration field, as well as the improvement of response characteristics of the dosemeters.

Journal Articles

Characteristics of a promising tritium process monitor detecting bremsstrahlung X-rays

Shu, Wataru; Matsuyama, Masao*; Suzuki, Takumi; Nishi, Masataka

Nuclear Instruments and Methods in Physics Research A, 521(2-3), p.423 - 429, 2004/04

 Times Cited Count:19 Percentile:75.21(Instruments & Instrumentation)

The characteristics of a promising tritium process monitor using a NaI(Tl) scintillation detector for X-rays was examined with pure tritium in a concentration range of 10$$^{2}$$-10$$^{8}$$GBq/m$$^{3}$$. The measurement of tritium concentration was achieved by observing the bremsstrahlung X-rays generated by the interaction between the tritium beta particles and a gold film coated on the inside of beryllium window. A linear relationship between the counting rate of bremsstrahlung X-rays and the tritium concentration was observed for tritium concentration range of 10$$^{2}$$-10$$^{6}$$GBq/m$$^{3}$$, and the sensitivity of the monitor was determined to be about 0.5GBq/m$$^{3}$$ per cpm in this concentration range. The characteristics were also investigated with a tritium mixture diluted with deuterium (atomic ration of tritium: 0.83%), and $$^{3}$$He release from a uranium bed during heating was traced with this monitor.

Journal Articles

Study on advancement of ${it in vivo}$ counting using mathematical simulation

Kinase, Sakae

RIST News, (37), p.10 - 19, 2004/03

no abstracts in English

Journal Articles

Revision of JIS Z 4511 and the present and future status of calibration of practical radiation protection instruments, 1

Murakami, Hiroyuki; Minami, Kentaro*

Radioisotopes, 53(3), p.197 - 205, 2004/03

no abstracts in English

Journal Articles

Single-ended pelletron accelerator at JAERI-Tokai

Shimizu, Shigeru; Fujii, Katsutoshi; Kajimoto, Yoichi; Kawasaki, Tomokatsu; Yamamoto, Hideaki

Dai-16-Kai Tandemu Kasokuki Oyobi Sono Shuhen Gijutsu No Kenkyukai Hokokushu, p.32 - 35, 2004/02

no abstracts in English

Journal Articles

Evaluation of energy responses for neutron dose-equivalent meters made in Japan

Saegusa, Jun; Yoshizawa, Michio; Tanimura, Yoshihiko; Yoshida, Makoto; Yamano, Toshiya*; Nakaoka, Hiroshi*

Nuclear Instruments and Methods in Physics Research A, 516(1), p.193 - 202, 2004/01

 Times Cited Count:16 Percentile:70(Instruments & Instrumentation)

Energy responses of three types of Japanese rem counters were evaluated by Monte Carlo simulations and measurements. The energy responses for thermal neutrons, monoenergetic neutrons with energies up to 15.2 MeV were evaluated as well as for neutrons from such radionuclide sources as $$^{252}$$Cf. The calculated results were corroborated with the measured ones. Angular dependence of the response and dose equivalent response was also evaluated. As a result, the reliable energy responses were obtained by careful simulations of the proportional counter, moderator and absorber of the rem counters. Furthermore, discussions were made about the relationship between pressure of counting gas and sensitivity of the rem counter. By using the obtained responses, relations of predicted readings of the rem counters and true dose equivalent were studied for various workplace spectra.

Journal Articles

Lung counting for $$^{241}$$Am in the lung

Kinase, Sakae; Oi, Yoshihiro; Sekiguchi, Masato

Radioisotopes, 52(8), p.378 - 382, 2003/08

no abstracts in English

Journal Articles

Rise-to-power test of the HTTR (High Temperature Engineering Test Reactor)

Fujikawa, Seigo; Okubo, Minoru; Nakazawa, Toshio; Kawasaki, Kozo; Iyoku, Tatsuo

Nihon Genshiryoku Gakkai Wabun Rombunshi, 1(4), p.361 - 372, 2002/12

no abstracts in English

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

JAEA Reports

Practical use of control rod calibration system with the inverse kinetices method

Yamanaka, Haruhiko; Hayashi, Kazuhiko; Motohashi, Jun; Kawashima, Kazuhito; Ichimura, Toshiyuki; Tamai, Kazuo; Takeuchi, Mitsuo

JAERI-Tech 2001-084, 110 Pages, 2002/01

JAERI-Tech-2001-084.pdf:10.15MB

no abstracts in English

Journal Articles

Evaluation of neutron dosemeter responses to various neutron fields

Saegusa, Jun; Yoshizawa, Michio; Tanimura, Yoshihiko; Yoshida, Makoto

Radioisotopes, 51(1), p.26 - 33, 2002/01

no abstracts in English

Journal Articles

Present status of FRS of JAERI

Yoshizawa, Michio; Saegusa, Jun; Tanimura, Yoshihiko; Yoshida, Makoto

Proceedings of 14th Meeting of Consultative Committee for Ionizing Radiation, 5 Pages, 2002/00

no abstracts in English

Journal Articles

Application of Monte Carlo simulations for evaluating efficiency curves of Ge detector

Saegusa, Jun

Hokeikyo Nyusu, (28), p.2 - 5, 2001/10

no abstracts in English

Journal Articles

Ionization chamber system for calibration of $$^{60}$$Co $$gamma$$-ray high dose rate at radiation processing level

Kojima, Takuji; Tachibana, Hiroyuki; Haneda, Noriyuki; Kaneko, Hirohisa; Haruyama, Yasuyuki; Tanaka, Ryuichi*

Radioisotopes, 50(7), p.291 - 300, 2001/07

Plaque type $${}^{60}$$Co $$gamma$$-ray sources having wide radiation field with high absorbed dose rates ranging of about 100$$sim$$10,000Gy/h is widely used in radiation processing e.g. radiation sterilization of health care products. Calibration of such radiation processing doses or dose rates is not easy to be performed at the present standard dosimetry laboratories, since characteristics of most of their radiation field can provide collimated gamma-rays from a point source and/or lower dose rates, which are quite different from those of panoramic (uncollimated) radiation fields used in radiation processing. The high-dose calibration technique using a parallel-plate ionization chamber system has developed in the JAERI dose calibration facility. The facility equips two $${}^{60}$$Co $$gamma$$-ray plaque sources covering wide dose-rate range of 5$$sim$$20,000 Gy/h which have overlapping dose-rate region with that at the National Institute of Advanced Industrial Science and Technology(AIST), the national standard Dosimetry laboratory in Japan. Consistency of dose calibration results at JAERI and those at AIST was verified without additional correction regarding to difference in characteristics of radiation fields involving current/exposure -rate conversion coefficients given in the dose rate level of 10$$sim$$100 Gy/h at the AIST and high-dose rates of 5$$sim$$20,000 Gy/h at JAERI. It demonstrates our dose traceability to the AIST from the technical point of view. The dose calibration at JAERI covers the high-dose range of 0.5 to $$1.60times{10}^5$$ Gy with uncertainty of $$pm$$2.2% at 95% confidence level.

Journal Articles

Accomplishment of constructing facility of calibration standards for neutrons

Yoshida, Makoto; Saito, Kimiaki

Nihon Genshiryoku Gakkai-Shi, 43(4), P. 311, 2001/04

no abstracts in English

112 (Records 1-20 displayed on this page)