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Journal Articles

The Role of high-injection effects on the transient ion beam induced current response of high-speed photodetectors

Laird, J. S.; Hirao, Toshio; Onoda, Shinobu*; Kamiya, Tomihiro

Nuclear Instruments and Methods in Physics Research B, 219-220, p.1015 - 1021, 2004/06

 Times Cited Count:7 Percentile:51.54(Instruments & Instrumentation)

no abstracts in English

Journal Articles

Present Status of Monte Carlo Seminar for Sub-criticality Safety Analysis in Japan

Sakurai, Kiyoshi; Nojiri, Ichiro*

JAERI-Conf 2003-019, p.855 - 857, 2003/10

This paper provides overview of sub-criticality safety analysis seminar (July 2000-July 2003, JAERI, total 40 engineers from universities, research institutes and enterprises) for nuclear fuel cycle facility with the Monte Carlo method in Japan. MCNP-4C2 system (MS-DOS version) was installed in each note-type personal computer. Fundamental theory of reactor physics and Monte Carlo simulation including MCNP-4C manual was lectured. Effective neutron multiplication factor and neutron spectrum were calculated for JCO deposit tank, JNC uranium solution storage tank, JNC plutonium solution storage tank and JAERI TCA core. In the seminar, methodology of safety management for nuclear fuel cycle facility was discussed in order to prevent criticality accident.

JAEA Reports

Effects of volume fraction and non-uniform arrangement of water moderator on reactivity

Cao, X.; Suzaki, Takenori; Kugo, Teruhiko; Mori, Takamasa

JAERI-Tech 2003-069, 36 Pages, 2003/08

JAERI-Tech-2003-069.pdf:3.77MB

From the viewpoint of nuclear criticality safety of fuel rod storage and transport, a series of critical experiments concerning effects of water hole size, water gap width, water-to-fuel volume ratio and non-uniform arrangement of water moderator have been performed at the Tank-type Critical Assembly (TCA) of Japan Atomic Energy Research Institute. In the present study, the effects of volume fraction and non-uniform arrangement of water moderator on reactivity are evaluated by the water level worth method and analyzed by the SRAC code. Error sources of experiments and calculations are discussed, especially for an energy group model. The calculation results of diffusion model with 17-group model show good agreement with the experiment results within a few dozen cents.

Journal Articles

Program of in-pile IASCC testing under the simulated actual plant condition; Thermohydraulic design study of saturated temperature capsule for IASCC irradiation test

Ide, Hiroshi; Matsui, Yoshinori; Nagao, Yoshiharu; Komori, Yoshihiro; Itabashi, Yukio; Tsuji, Hirokazu; Tsukada, Takashi; Nagata, Nobuaki*; Dozaki, Koji*; Takiguchi, Hideki*

Proceedings of 11th International Conference on Nuclear Engineering (ICONE-11) (CD-ROM), 7 Pages, 2003/04

The advanced water chemistry controlled irradiation research device has been developed in JAERI to perform irradiation tests for research on IASCC. The irradiation device consists of the SATCAP (Saturated Temperature Capsule) inserted into the JMTR core and the water control unit installed out-of-core. Regarding the SATCAP, thermohydraulic design of the SATCAP was performed aiming at controlling the specimen temperature with high accuracy and increasing water flow velocity on the specimen surface to improve the controllability of water chemistry. As a result of irradiation test using the new type SATCAP, each specimen temperature and water chemistry were able to be controlled as designed.

JAEA Reports

Analytical study of two-region TCA critical experiments with PWR-type MOX fuel by using Monte Carlo code MVP

Rahman, M.*; Suzaki, Takenori; Mori, Takamasa

JAERI-Research 2003-007, 68 Pages, 2003/03

JAERI-Research-2003-007.pdf:2.48MB

no abstracts in English

Journal Articles

Effect of higher-harmonic flux in exponential experiment for subcriticality measurement

Yamamoto, Toshihiro; Miyoshi, Yoshinori; Tonoike, Kotaro; Okamoto, Hajime*; Ida, Toshikazu*; Aoki, Shigeaki*

Journal of Nuclear Science and Technology, 40(2), p.77 - 83, 2003/02

 Times Cited Count:5 Percentile:60.42(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Adjustment of total delayed neutron yields of $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu by using results of in-pile measurements of effective delayed neutron fraction

Sakurai, Takeshi; Okajima, Shigeaki

Proceedings of International Conference on the New Frontiers of Nuclear Technology; Reactor Physics, Safety and High-Performance Computing (PHYSOR 2002) (CD-ROM), 12 Pages, 2002/10

The cross section adjustment method was applied to total delayed neutron yields of $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction $$beta_{eff}$$ at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. Furthermore, to validate these adjusted delayed neutron yields, analyses were performed for the $$beta_{eff}$$ experiments at ZPR fast critical facility. These adjusted yields brought a reduction of uncertainty of calculated $$beta_{eff}$$ and an improvement in agreement of $$beta_{eff}$$ between experiment and calculation.

Journal Articles

Evaluation of Delayed Neutron Data for JENDL-3.3

Yoshida, Tadashi*; Okajima, Shigeaki; Sakurai, Takeshi; Nakajima, Ken; Yamane, Tsuyoshi; Katakura, Junichi; Tahara, Yoshihisa*; Zukeran, Atsushi*; Oyamatsu, Kazuhiro*; Osawa, Takaaki*; et al.

Journal of Nuclear Science and Technology, 39(Suppl.2), p.136 - 139, 2002/08

no abstracts in English

Journal Articles

Adjustment of total delayed neutron yields of $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu in JENDL-3.2 using benchmark experiments on effective delayed neutron fraction $$beta_{eff}$$

Sakurai, Takeshi; Okajima, Shigeaki

Journal of Nuclear Science and Technology, 39(1), p.19 - 30, 2002/01

 Times Cited Count:5 Percentile:62.25(Nuclear Science & Technology)

The cross section adjustment method was applied to total delayed neutron yields of $$^{235}$$U, $$^{238}$$U and $$^{239}$$Pu of the JENDL-3.2 file by using experimental results of effective delayed neutron fraction $$beta_{eff}$$ at six cores built in two fast critical facilities of the MASURCA and FCA and a thermal critical facility of the TCA to improve these yields. The adjustment was carried out on the yields given at several incident neutron energy points in the file. After the adjustment, the yield of $$^{238}$$U was almost uniformly decreased by about 3% below 7 MeV. The yield of $$^{239}$$Pu was increased by 2.6% and that of $$^{235}$$U was decreased by 0.9% at the thermal energy point, while the change of yield was less than 0.3% at the other energy points for these nuclides. By using these adjusted yields, the uncertainty of calculated $$beta_{eff}$$ was reduced and the agreement of $$beta_{eff}$$ between experiment and calculation was improved.

Journal Articles

Temperature dependence of heavy ion induced current transients in Si epilayer devices

Laird, J. S.; Hirao, Toshio; Onoda, Shinobu; Mori, H.; Ito, Hisayoshi

Proceedings of 6th European Conference on Radiation and its Effects on Components and System (RADECS 2001) (CD-ROM), 7 Pages, 2002/00

no abstracts in English

JAEA Reports

Study on reduced-moderation water reactor (RMWR) core design; Joint research report, FY1998-1999 (Joint research)

Research Group for Advanced Reactor System; Research Group for Reactor Physics; Research Group for Thermal and Fluid Engineering

JAERI-Research 2000-035, 316 Pages, 2000/09

JAERI-Research-2000-035.pdf:19.81MB

no abstracts in English

JAEA Reports

A Plan of reactor physics experiments for reduced-moderation water reactors with MOX fuel in TCA

Shimada, Shoichiro*; Akie, Hiroshi; Suzaki, Takenori; Okubo, Tsutomu; Usui, Shuji*; Shirakawa, Toshihisa*; Iwamura, Takamichi; Kugo, Teruhiko; Ishikawa, Nobuyuki

JAERI-Research 2000-026, 74 Pages, 2000/06

JAERI-Research-2000-026.pdf:4.07MB

no abstracts in English

Journal Articles

Precise determination of $$beta$$$$_{eff}$$ for water-moderated U and U-Pu cores by a method using buckling coefficient of reactivity

Suzaki, Takenori; Sakurai, Kiyoshi; Nakajima, Ken; Horiki, Oichiro*

Proceedings of 6th International Conference on Nuclear Criticality Safety (ICNC '99), 1, p.386 - 394, 1999/00

no abstracts in English

Journal Articles

Irradiation techniques under high pressurized water using hybrid type saturated temperature capsule in the JMTR

Matsui, Yoshinori; Niimi, Motoji; Hoshiya, Taiji; Tsukada, Takashi; Tsuji, Hirokazu

Journal of Nuclear Materials, 258-263, p.378 - 382, 1998/00

 Times Cited Count:0 Percentile:100

no abstracts in English

Journal Articles

Estimation of subcriticality with the computed values; Analysis using MCNP of experiment on coupled cores

Sakurai, Kiyoshi; Yamamoto, Toshihiro; Arakawa, Takuya*; *

Nippon Genshiryoku Gakkai-Shi, 40(5), p.380 - 386, 1998/00

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

Journal Articles

Journal Articles

Studies on burnup credit at JAERI

; Nomura, Yasushi; Suyama, Kenya

Proc. of Int. Conf. on the Phys. of Nucl. Sci. and Technol., 1, p.742 - 748, 1998/00

no abstracts in English

Journal Articles

Measurements and analyses of reactivity effect of fission product nuclides in epithermal energy range

Yamamoto, Toshihiro; Sakurai, Kiyoshi; Suzaki, Takenori; *; ; Horiki, Oichiro*

Journal of Nuclear Science and Technology, 34(12), p.1178 - 1184, 1997/12

 Times Cited Count:0 Percentile:100(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

Measurement of reactivity worths of Sm,Cs,Gd,Nd,Rh,Eu,B and Er aqueous solution samples

Komuro, Yuichi; Suzaki, Takenori; *; Sakurai, Kiyoshi; Horiki, Oichiro*

JAERI-Research 97-088, 19 Pages, 1997/11

JAERI-Research-97-088.pdf:0.86MB

no abstracts in English

JAEA Reports

Educational reactor-physics experiments with the critical assembly TCA

*; *; *; Horiki, Oichiro*; Suzaki, Takenori

JAERI-Review 97-014, 43 Pages, 1997/10

JAERI-Review-97-014.pdf:1.2MB

no abstracts in English

46 (Records 1-20 displayed on this page)