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Sato, Ikken; Yoshikawa, Shinji; Yamashita, Takuya; Shimomura, Kenta; Cibula, M.*; Mizokami, Shinya*
Nuclear Engineering and Design, 422, p.113088_1 - 113088_24, 2024/06
Moriguchi, Yuichi*; Sato, Yosuke*; Morino, Yu*; Goto, Daisuke*; Sekiyama, Tsuyoshi*; Terada, Hiroaki; Takigawa, Masayuki*; Tsuruta, Haruo*; Yamazawa, Hiromi*
KEK Proceedings 2021-2, p.21 - 27, 2021/12
no abstracts in English
Takahashi, Hiroshi*; Minami, Masayo*; Aramaki, Takafumi*; Handa, Hiroko*; Kokubu, Yoko; Ito, Shigeru*; Kumamoto, Yuichiro*
Radiocarbon, 61(6), p.1879 - 1887, 2019/12
Times Cited Count：2 Percentile：11.51(Geochemistry & Geophysics)Water sample for interlaboratory comparison (here after "comparison water") must have inalterable 
C concentration during the comparison campaign and inter-batches homogeneity. In this study, the procedure for preparing of comparison water was discussed. We employed that comparison waters were artificially made by mixing chemical reagents, controlling C concentration and chemical composition. We could prepare six comparison waters, having 1, 14, 37, 56, 72 and 100 pMC, respectively. The stable carbon isotopic values and chemical compositions of some batches were measured to exanimate the inter- batches homogeneity. The C discrepancies among the batches were negligible for the inter-laboratory comparison. Finally, the results of trial comparison in Japan will be presented. Most of C results of CO
extracted by six laboratories showed good agreements each other.
Yamamoto, Hideaki; Yoshizawa, Michio; Murakami, Hiroyuki; Momose, Takumaro*; Tsujimura, Norio*; Kanai, Katsuta*; Cruz-Suarez, R.*
Radiation Protection Dosimetry, 125(1-4), p.88 - 92, 2007/07
Times Cited Count：0 Percentile：0.01(Environmental Sciences)The purpose of this paper is to discuss the results of the third intercomparison exercise of external radiation dosimetry organized under the Regional Cooperative Agreement (RCA) in the East Asia region of the International Atomic Energy Agency (IAEA). Twenty five laboratories from 16 member states participated in the exercise. Japan Atomic Energy Research Institute (JAERI) and Japan Nuclear Cycle Development Institute (JNC) arranged the standard irradiation of the participants' dosimeters. The results of the measurements of the irradiated dosimeters for the determination of external doses were satisfactory for all participants, demonstrating good performance in their external dosimetry.
Kallenbach, A.*; Asakura, Nobuyuki; Kirk, A.*; Korotkov, A.*; Mahdavi, M. A.*; Mossessian, D.*; Porter, G. D.*
Journal of Nuclear Materials, 337-339, p.381 - 385, 2005/03
Times Cited Count：66 Percentile：96.55(Materials Science, Multidisciplinary)Edge profile data for H-mode discharges in 6 tokamaks have been analysed with the main focus on the edge density profile as well as electron temperature and density gradient lengths and steep gradient zone widths. A uniform procedure of data treatment and assignment of the separatrix position via power balance allowed to put the multi-machine data on an even base. The machine size appears to be the leading parameter for the width of the steep edge transport barrier gradient zone, as well as for the temperature decay length at the separatrix. Effects associated with neutral penetration physics are visible in the edge density profile.
Saibene, G.*; Hatae, Takaki; Campbell, D. J.*; Cordey, J. G.*; la Luna, E. de.*; Giroud, C.*; Guenther, K.*; Kamada, Yutaka; Kempenaars, M. A. H.*; Loarte, A.*; et al.
Plasma Physics and Controlled Fusion, 46(5A), p.A195 - A205, 2004/05
Times Cited Count：10 Percentile：31.99(Physics, Fluids & Plasmas)Towards establishment of the control scheme and evaluation of the H-mode pedestal structure and behavior of the Edge Localized Mode (ELM) in ITER, we carried out an comparison experiment among the two large tokamaks (JT-60 and JET) for the first time. This paper report the initial results. In both devices, the same plasma shape was adopted and the three non-dimensional parameters (beta, normalized gyro radius and the normalized collisionality) were set identical. The pedestal width was almost similar in the two devices, however the pressure gradient was higher in JET by a factor of 1.5. The possible reason is a small aspect ration in JET.
Billard, I.*; Ansoborlo, E.*; Apperson, K.*; Arpigny, S.*; Azenha, M.-E.*; Birch, D.*; Bros, P.*; Burrows, H. D.*; Choppin, G. R.*; Couston, L.*; et al.
Applied Spectroscopy, 57(8), p.1027 - 1038, 2003/08
Times Cited Count：50 Percentile：88.17(Instruments & Instrumentation)no abstracts in English
Sakurai, Kiyoshi; Yamamoto, Toshihiro
Nihon Genshiryoku Gakkai Wabun Rombunshi, 2(2), p.202 - 214, 2003/06
Monte Carlo Working Group of Special Committee on Nuclear Code Evaluation at JAERI investigated present status of application of Monte Carlo Calculation for large nuclear facilities in Japan. Application of Monte Carlo method has already been popular even to large facilities, but the calculated results are not compared with measured datain most of those applications. The authors believe that accuracy and precision of the method should be examined through comparisons with measured data, and that databases of measured data at experimental or commercial facilities should be developed for further comparison with the analysis results.
Shinohara, Nobuo; Yamamoto, Yoichi; Inoue, Yoji; Kumata, Masahiro; Oda, Tetsuzo; Uchikoshi, Takako*; Hokida, Takanori; Hirota, Naoki*; Nakahara, Yoshinori; Usuda, Shigekazu
Dai-23-Kai Kaku Busshitsu Kanri Gakkai Nihon Shibu Nenji Taikai Rombunshu, p.45 - 52, 2002/12
no abstracts in English
Inoue, Tomio*; Hayakawa, Kazushige*; Shiotari, Harutaka*; Takada, Eiichi*; Torikoshi, Masami*; Nagasawa, Kiyoshi*; Hagiwara, Kazuo*; Yanagisawa, Kazuaki
Journal of Nuclear Science and Technology, 39(10), p.1114 - 1119, 2002/10
Times Cited Count：4 Percentile：29.2(Nuclear Science & Technology)no abstracts in English
Suyama, Kenya; Katakura, Junichi; Kiyosumi, Takehide*; Kaneko, Toshiyuki*; Nomura, Yasushi
Journal of Nuclear Science and Technology, 39(1), p.82 - 89, 2002/01
Times Cited Count：8 Percentile：47.85(Nuclear Science & Technology)no abstracts in English
Kume, Tamikazu
Shin Seiki No Shokuhin Kako Gijutsu, p.91 - 100, 2002/00
no abstracts in English
- matrixToh, Yosuke; Oshima, Masumi; Hatsukawa, Yuichi; Hayakawa, Takehito; Shinohara, Nobuo
Journal of Radioanalytical and Nuclear Chemistry, 250(2), p.373 - 376, 2001/11
Times Cited Count：17 Percentile：74.75(Chemistry, Analytical)no abstracts in English
*
JNC TJ6420 2000-005, 109 Pages, 2000/07
JNC-TJ6420-2000-005.pdf:3.16MB
no abstracts in English
Sakai, Takaaki; *; Ohshima, Hiroyuki; Yamaguchi, Akira
JNC TN9400 2000-033, 94 Pages, 2000/04
JNC-TN9400-2000-033.pdf:4.36MB
The feasibility study on several concepts for the commercial fast breeder reactor(FBR) in future has been conducted in JNC for the kinds of possible coolants and fuel types to confirm the direction of the FBR developments in Japan. ln this report, Lead and Lead-Bismuth eutectic coolants were estimated for the decay heat removal characteristics by the comparison with sodium coolant that has excellent features for the heat transfer and heat transport performance. Heavy liquid metal coolants, such as Lead and Lead-Bismuth, have desirable chemical inertness for water and atmosphere. Therefore, there are many economical plant proposals without an intermediate heat transport system that prevents the direct effect on a reactor core by the chemical reaction between water and the liquid metal coolant at the hypocritical tube fairer accidents in a steam generator. ln this study, transient analyses on the thermal-hydraulics have been performed for the decay heat removal events in "Equivalent plant" with the Lead, Lead-Bismuth and Sodium coolant by using Super-COPD code. And a resulted optimized lead cooled plant in feasibility study was also analyzed for the comparison. ln conclusion, it is become clear that the natural circulation performance, that has an important roll in passive safety characteristic of the reactor, is more excellent in heavy liquid metals than sodium coolant during the decay heat removal transients. However, we need to conform the heat transfer reduction by the oxidize film or the corrosion products expected to appear on the heat transfer surface in the Lead and Lead-Bismuth circumstance.
Shiba, Tsuyoshi*; Kamezaki, Hiroshi*; Yuyama, Tomonori*; *
JNC TJ9400 2000-012, 92 Pages, 2000/02
JNC-TJ9400-2000-012.pdf:3.18MB
This research aims to develop a system in which aspects necessary for FBR cycle and overall comparison of evaluation items (economy, safety etc.) are evaluated quantitatively and objectively as a part of Nuclear Cycle development's research project of the FBR cycle for practical use. There are various methods in the decision-making support. In this particular situation, features of each method were evaluated based on the analysis of cases with each method. Subsequently we constructed overall evaluation method by combining Analytic Hierarchy Process (AHP), Multi-attribution Utility Function Method (MUF) and Cut-off Method. This method has variation in evaluation items, transparency in evaluation process and uncompensation. The six aspects of evaluation are economy, effectiveness of resource use, proliferation resistance, environmental effectiveness, safety, and research and development. The evaluation items and the evaluation index of each aspect were hierarchized and the evaluation structure was constructed. In the present study effect function for each evaluation index and pair comparison for examining significance of each item were utilized to select prospective systems for FBR cycle experimentally. The result confirmed reliability of our general assessment system as a decision-making support system for FBR system.
Takahashi, Tomoyuki*; Takebe, Shinichi; Kimura, Hideo; Matsuzuru, Hideo; Yasuda, Hiroshi*; Uchida, Shigeo*; Saeki, Akiyoshi*; Mahara, Yasunori*; Sasaki, Noriyuki*; Ashikawa, Nobuo*; et al.
KURRI-KR-44, p.169 - 176, 2000/02
no abstracts in English
Oki, Shigeo
JNC TN9400 2000-007, 77 Pages, 1999/12
JNC-TN9400-2000-007.pdf:2.17MB
Comparative study for various core concepts is being carried out in a frame work of the study for minor actinide (MA) transmutation using a fast reactor. Different fuel types (Oxide, Nitride, Metal) and coolants (Sodium, Lead) were investigated. It is found that neither nitride nor metal-fueled core has significantly more excellent efficiency for MA transmutation comparing with an oxide-fueled core when the basic performance of these cores as a power reactor are fixed. The MA transmutation Properties of lead-cooled fast reaetor (BREST-300) and sodium-cooled fast reactor (3800MWth large core) were compared. The sodium-cooled reactor surpasses BREST-300 on the MA transmutation rate. Meanwhile, it is found that BREST-300 is excellent from the viewpoint of loading much more MA in the core to attain larger MA transmutation amount. The effect of MA to coolant void reactivity is considered by the sensitivity analysis. It is found that the lead void reactivity has different sensible energy regions on MA nuclides from those for the sodium void reactivity.
Tamaki, Hitoshi; *; ; Nomura, Yasushi
JAERI-Tech 98-008, 43 Pages, 1998/03
no abstracts in English
