Refine your search:     
Report No.
 - 
Search Results: Records 1-20 displayed on this page of 36

Presentation/Publication Type

Initialising ...

Refine

Journal/Book Title

Initialising ...

Meeting title

Initialising ...

First Author

Initialising ...

Keyword

Initialising ...

Language

Initialising ...

Publication Year

Initialising ...

Held year of conference

Initialising ...

Save select records

JAEA Reports

Evaluation of the minimum critical amount for heterogeneous lattice systems composed of fuel rods utilized in low-power water-moderated research and test reactors by using continuous-energy Monte Carlo code MVP with JENDL-4.0

Yanagisawa, Hiroshi

JAEA-Technology 2021-023, 190 Pages, 2021/11

JAEA-Technology-2021-023.pdf:5.25MB

Computational analyses on nuclear criticality characteristics were carried out for heterogeneous lattice systems composed of water moderator and fuel rods utilized in low-power research and test reactors, in which the depletion of fuel due to burnup is relatively small, by using the continuous-energy Monte Carlo code MVP Version 2 with the evaluated nuclear data library JENDL-4.0. In the analyses, the minimum critical number of fuel rods was evaluated using calculated neutron multiplication factors for the heterogeneous systems of the uranium dioxide fuel rod in the Static Experiments Critical Facility (STACY) and the Tank-type Critical Assembly (TCA), and the uranium-zirconium hydride fuel rod in the Nuclear Safety Research Reactor (NSRR). In addition, six sorts of the ratio of reaction rates, which are components of neutron multiplication factors, were calculated in the analyses to explain the variation of neutron multiplication factors with the ratio of water moderator to fuel volume in a unit fuel rod cell. Those results of analyses are considered to be useful for the confirmation of reasonableness and validity of criticality safety measures as data showing criticality characteristics for water-moderated heterogeneous lattice systems composed of the existing fuel rods in research and test reactors, of which criticality data are not sufficiently provided by the Criticality Safety Handbook.

Journal Articles

The Framing effects of compensation and taboo trade-offs on acceptance of NIMBY Facility; A Scenario experiment of high level radioactive waste geological repository

Iino, Mari*; Onuma, Susumu*; Hirose, Yukio*; Osawa, Hideaki; Otomo, Shoji*

Nihon Risuku Kenkyu Gakkai-Shi, 29(2), p.95 - 102, 2019/10

The purpose of this research is to investigate the effects of compensation framing on acceptance of a high level radioactive waste (HLW) geological repository. The results demonstrated that there were no main effects of condition, which suggested that the framing of compensation had no significant impact on acceptance of a HLW geological repository.

Journal Articles

Comparative study on prediction accuracy improvement methods with the use of integral experiments for neutronic characteristics of fast reactors

Yokoyama, Kenji; Kitada, Takanori*

Proceedings of 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) (CD-ROM), p.1221 - 1230, 2018/04

no abstracts in English

Journal Articles

Dimension-reduced cross-section adjustment method based on minimum variance unbiased estimation

Yokoyama, Kenji; Yamamoto, Akio*; Kitada, Takanori*

Journal of Nuclear Science and Technology, 55(3), p.319 - 334, 2018/03

 Times Cited Count:8 Percentile:62.29(Nuclear Science & Technology)

A new formulation of the cross-section adjustment methodology with the dimensionality reduction technique has been derived. This new formulation is proposed as the dimension reduced cross-section adjustment method (DRCA). Since the derivation of DRCA is based on the minimum variance unbiased estimation (MVUE), an assumption of normal distribution is not required. The result of DRCA depends on a user-defined matrix that determines the dimension reduced feature subspace. We have examine three variations of DRCA, namely DRCA1, DRCA2, and DRCA3. Mathematical investigation and numerical verification have revealed that DRCA2 is equivalent to the currently widely used cross-section adjustment method. Moreover, DRCA3 is found to be identical to the cross-section adjustment method based on MVUE, which has been proposed in the previous study.

Journal Articles

Conductance of a long rectangular channel; Pressure dependence

Ogiwara, Norio; Hikichi, Yusuke*; Kamiya, Junichiro; Kinsho, Michikazu; Yoshida, Hajime*; Arai, Kenta*

Journal of the Vacuum Society of Japan, 60(12), p.475 - 480, 2017/12

Journal Articles

CsI(Tl)/Plastic phoswich detector enhanced in low-energy $$gamma$$-ray detection

Yamasoto, Kotaro; Tsutsumi, Masahiro; Oishi, Tetsuya*; Yoshizawa, Michio; Yoshida, Makoto

Nuclear Instruments and Methods in Physics Research A, 550(3), p.609 - 615, 2005/09

 Times Cited Count:5 Percentile:41.01(Instruments & Instrumentation)

A phoswich detector composed of a thin plate CsI(Tl) scintillator and a plastic scintillator (BC-400) has been designed and evaluated to improve the sensitivity in the low-energy region of large-area plastic scintillation detector. Applicability of the CsI(Tl)/Plastic phoswich detector was examined on radioactivity measurement of massive and large-area materials. The rise-time discrimination technique was applied in order to further improve the minimum detectable activity in the low-energy region. On the basis of the estimation of minimum detectable activity, it was made clear that the energy range of large-area plastic scintillation detector can be expanded down to a few tens of keV by adding a thin plate CsI(Tl) scintillator.

Journal Articles

Benchmark analyses of neutron streaming experiments for proton accelerator facilities

Nakano, Hideo*; Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo*; Tayama, Ryuichi*; Handa, Hiroyuki*; Hayashi, Katsumi*

Journal of Nuclear Science and Technology, 41(Suppl.4), p.50 - 53, 2004/03

In order to estimate accuracy of the various calculation methods for the neutron streaming through a maze and duct in proton accelerator facilities, we performed benchmark analyses by using the radiation shielding design codes. According to the results of the benchmark analyses, it is concluded that NMTC/MCNP, MCNPX and DUCT-III are applicable to actual calculation of the duct-streaming radiations for J-PARC.

Journal Articles

Analyses of high energy neutron streaming experiments using DUCT-III

Masukawa, Fumihiro; Nakashima, Hiroshi; Sasamoto, Nobuo; Nakano, Hideo*; Tayama, Ryuichi*

Journal of Nuclear Science and Technology, 39(Suppl.2), p.1268 - 1271, 2002/08

no abstracts in English

Journal Articles

First-principles calculations of Magnetic Circular Dichroism spectra of nonmagnetic elements in ferromagnetic ordered alloys

Yamaguchi, Masatake; Asano, S.*

Nihon Oyo Jiki Gakkai-Shi, 25(4-Part2), p.659 - 662, 2001/04

no abstracts in English

Journal Articles

Development and performance of high speed processing system of magnetohydrodynamic equilibria for discharge analyses on the JT-60 tokamak

Hasegawa, Yukihiro*; Nakamura, Yukiharu; Shirai, Hiroshi; Hamamatsu, Kiyotaka; Harada, Hiro; Kikuchi, Mitsuru; *

Nihon Genshiryoku Gakkai-Shi, 41(1), p.48 - 56, 1999/00

 Times Cited Count:2 Percentile:21.16(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

AVS user's guide on the basis of practice

*; Kato, Katsumi*; Kume, Etsuo;

JAERI-Tech 97-028, 37 Pages, 1997/07

JAERI-Tech-97-028.pdf:1.32MB

no abstracts in English

JAEA Reports

Development of animation processing system

Kato, Katsumi*; Watanabe, Tadashi; *;

JAERI-Tech 95-014, 42 Pages, 1995/03

JAERI-Tech-95-014.pdf:1.22MB

no abstracts in English

JAEA Reports

Development of the module inspection system for new standarized radiation monitoring modules

; Shimizu, Kazuaki; ; Chida, Toru; Mizugaki, Toshio; Oi, Yoshihiro

JAERI-Tech 94-023, 106 Pages, 1994/10

JAERI-Tech-94-023.pdf:3.43MB

no abstracts in English

JAEA Reports

Effect of cold work on creep properties of Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-Research 94-004, 30 Pages, 1994/08

JAERI-Research-94-004.pdf:2.99MB

no abstracts in English

JAEA Reports

Creep properties of 20% cold worked Hastelloy XR

Kurata, Yuji; Nakajima, Hajime

JAERI-M 94-022, 28 Pages, 1994/02

JAERI-M-94-022.pdf:0.9MB

no abstracts in English

JAEA Reports

Experimental study on DNB heat flux of plate-type fuel in pressurized condition

; ; Kaminaga, Masanori; Ishitsuka, Etsuo; ; Sudo, Yukio; Saito, Minoru;

JAERI-M 92-097, 61 Pages, 1992/07

JAERI-M-92-097.pdf:2.42MB

no abstracts in English

JAEA Reports

Design of H$$^{infty}$$-filter to estimate a linear system state in the frequency domain

Suzuki, Katsuo; Shimazaki, Junya; Shinohara, Yoshikuni

JAERI-M 91-105, 43 Pages, 1991/07

JAERI-M-91-105.pdf:0.85MB

no abstracts in English

JAEA Reports

Visualization of computed results

*;

JAERI-M 90-100, 49 Pages, 1990/07

JAERI-M-90-100.pdf:1.29MB

no abstracts in English

JAEA Reports

Journal Articles

36 (Records 1-20 displayed on this page)