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Journal Articles

Systematic effects on cross section data derived from reaction rates in reactor spectra and a re-analysis of $$^{241}$$Am reactor activation measurements

$v{Z}$erovnik, G.*; Schillebeeckx, P.*; Becker, B.*; Fiorito, L.*; Harada, Hideo; Kopecky, S.*; Radulovic, V.*; Sano, Tadafumi*

Nuclear Instruments and Methods in Physics Research A, 877, p.300 - 313, 2018/01

 Times Cited Count:3 Percentile:45.99(Instruments & Instrumentation)

Methodologies to derive cross section data from spectrum integrated reaction rates were studied. The Westcott convention and some of its approximations were considered. The accuracy of the results strongly depends on the assumptions that are made about the neutron energy distribution, which is mostly parameterised as a sum of a thermal and an epi-thermal component. Resonance integrals derived from such data can be strongly biased. When the energy dependence of the cross section is known and information about the neutron energy distribution is available, a method to correct for a bias on the cross section at thermal energy is proposed. Reactor activation measurements to determine the thermal $$^{241}$$Am(n, $$gamma$$) cross section reported in the literature were reviewed, where the results were corrected to account for possible biases. These data combined with results of time-of-flight measurements give a capture cross section 720 (14) b for $$^{241}$$Am(n, $$gamma$$) at thermal energy.

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

Dissolved forms of $$^{90}$$Sr, $$^{239+240}$$Pu and $$^{241}$$Am in the Sahan river waters from the Chernobyl area

Nagao, Seiya; Matsunaga, Takeshi; Fujitake, Nobuhide*; Amano, Hikaru

Proceedings of the International Workshop on Distribution and Speciation of Radionuclides in the Environment, p.162 - 168, 2000/00

no abstracts in English

Journal Articles

Measurement of fission product yields from neutron-induced fission of americium-241

Shinohara, Nobuo; Hatsukawa, Yuichi; ; Kono, Nobuaki

Journal of Nuclear Science and Technology, 36(3), p.232 - 241, 1999/03

 Times Cited Count:3 Percentile:29.56(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Sorption characteristics of $$^{237}$$Np,$$^{238}$$Pu and $$^{241}$$Am in sedimentary materials

Tanaka, Tadao; Muraoka, Susumu

Journal of Radioanalytical and Nuclear Chemistry, 240(1), p.177 - 182, 1999/00

 Times Cited Count:11 Percentile:65.07(Chemistry, Analytical)

no abstracts in English

JAEA Reports

Evaluation of scattered neutrons in fast neutron calibration field using $$^{252}$$Cf and $$^{241}$$Am-Be neutron source

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

JAERI-Tech 98-005, 65 Pages, 1998/03

JAERI-Tech-98-005.pdf:2.32MB

no abstracts in English

Journal Articles

Preparation of source and sealed absorber holder for $$^{237}$$Np and $$^{238}$$U Moessbauer measurements

Nakada, Masami; Saeki, Masakatsu; ; Tsutsui, Satoshi*

Journal of Radioanalytical and Nuclear Chemistry, 232(1-2), p.201 - 207, 1998/00

 Times Cited Count:8 Percentile:58.55(Chemistry, Analytical)

no abstracts in English

Journal Articles

Radiochemical determination of neutron capture cross sections of $$^{241}$$Am

Shinohara, Nobuo; ; ; Kono, Nobuaki

Journal of Nuclear Science and Technology, 34(7), p.613 - 621, 1997/07

 Times Cited Count:29 Percentile:88.95(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Sorption of $$^{60}$$Co,$$^{85}$$Sr,$$^{137}$$Cs,$$^{237}$$Np and $$^{241}$$Am on soil under coexistence of humic acid; Effects of molecular size of humic acid

Tanaka, Tadao;

Materials Research Society Symposium Proceedings, Vol.353, 0, p.1013 - 1020, 1995/00

no abstracts in English

Oral presentation

Measurement and calculation analysis of shielding material's performance for MOX containing americium

Okada, Toyofumi; Shibanuma, Tomohiro; Honda, Fumiya; Komeno, Akira; Kikuno, Hiroshi

no journal, , 

$$^{241}$$Am is generated by beta-decay of $$^{241}$$Pu. In the case of treating MOX, it is important for shielding about 60keV gamma-ray emitted by $$^{241}$$Am. Also getting dose rate data of MOX containing $$^{241}$$Am is valuable. In this work, we measured gamma-ray dose rate from MOX containing $$^{241}$$Am by changing thickness of shielding materials and range between MOX and measuring instruments. Also we confirmed that calculating analysis is useful for evaluation of shielding material's performance.

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