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Asahi, Yoshiro; Suzudo, Tomoaki; Ishikawa, Nobuyuki; Nakatsuka, Toru
Nuclear Science and Engineering, 152(2), p.219 - 235, 2006/02
Times Cited Count：0 Percentile：0.01(Nuclear Science & Technology)An analysis of a BWR turbine trip experiment was performed with the THYDE-NEU code. The plant was treated as a closed coolant system whose pressure ranges to the atmospheric pressure. To simulate an entire plant, it was found necessary to have the moisture separator model and to account for reversible pressure drops at a junction with an area change. A spatial kinetics model without a notion of reactivity was applied. It was confirmed that THYDE-NEU can perform a coupled neutronic and thermal-hydraulic null transient at the hot full power. Among factors influencing spatial kinetics in the turbine trip were the temporal behavior of the bypass valve opening, the thermal non-equilibrium model and the manner in which to express the coolant density used in the table look-up of cross sections. By adjusting these factors, it was found possible to generate the scram signal when the core averaged LPRM output reached the prescribed value. The other calculated results also were found satisfactorily in agreement with the experimental results.
Yamauchi, Michinori*; Ochiai, Kentaro; Morimoto, Yuichi*; Wada, Masayuki*; Sato, Satoshi; Nishitani, Takeo
Radiation Protection Dosimetry, 116(1-4), p.542 - 546, 2005/12
Times Cited Count：3 Percentile：24.22(Environmental Sciences)no abstracts in English
Nakajima, Ken; Yamane, Yuichi; Miyoshi, Yoshinori
JAERI-Data/Code 2002-004, 42 Pages, 2002/03
JAERI-Data-Code-2002-004.pdf:1.51MB
no abstracts in English
Sakurai, Kiyoshi; Ueki, Kotaro*
Nihon Genshiryoku Gakkai-Shi, 43(4), p.351 - 352, 2001/04
no abstracts in English
Sugino, Kazuteru; Iwai, Takehiko*;
JNC TN9400 2000-098, 182 Pages, 2000/07
JNC-TN9400-2000-098.pdf:5.74MB
In order to support the Russian excess weapons plutonium disposition, the international collaboration has been started between Japan Nuclear Cycle Development Institute (JNC) and Russian Institute of Physics and Power Engineering (IPPE). In the frame of the collaboration, JNC has carried out analyses on the BFS-62 assemblies that are constructed in the fast reactor critical experimental facility BFS-2 of IPPE. This report summarizes an experimental analysis on the BFS-62-1 assembly, which is the first core of the BFS-62 series. The core contains the enriched U0
fuel surrounded by the U0 blanket. The standard analytical method for fast reactors has been applied, which was used for the JUPITER and other experimental analyses. Due to the lack of the analytical data the 2D RZ core calculation was mainly used. The 3D XYZ core calculation was applied only for the preliminary evaluation. Further in terms of the utilization of the BFS experimental analysis data for the standard data base for FBR core design, consistency evaluation with JUPITER experimental analysis data has been performed using the cross-section adjustment method. As the result of analyses, good agreement was obtained between calculations and experiments for the criticality and the reaction rate ratio. However, it was found that accurate evaluation of the reaction rate distribution was impossible without exact consideration of the arrangement of the two types of sodium (with and without hydrogen impurity), which can be accommodated by the 3D core analysis, thus it was essentia1. In addition, it was clarifie that there was a room for an improvement of the result on the reaction rate distribution in the blanket and shielding regions. The application of the 3D core calculation improved the result on the control rod worth because 3D core model can more exactly consider the shape of the control rod. Furthermore it was judged that the result of the analysis on the sodium void reactivity .....
Dietze, K.
JNC TN9400 99-089, 20 Pages, 1999/11
The integral experiments performed at the Rossendorf fast-thermal coupled reactor RRR/SEG have been reanalyzed using the JNC route for reactor calculation JENDL3.2/SLAROM / CITATION / JOINT / PERKY. The Rossendorf experiments comprise sample reactivity measurements with pure fission products and structural material in five configurations with different neutron and adjoint spectra. The shapes of the adjoint spectra have been designed to get high sensitivities to neutron capture or the scattering effect. The calculated neutron and adjoint spectra are in good agreement with former results obtained with the European route JEF2.2/ECCO/ERANOS. The C/E-values of the central reactivity worths of samples under investigation are given. Deviations in the results of both routes are due to the different libraries, codes, and self-shielding treatments used in the calculations. Results outside of the error are discussed.
Ikeda, Yujiro; Konno, Chikara; Kosako, Kazuaki*; Oyama, Yukio; Maekawa, Fujio; Maekawa, Hiroshi; A.Kumar*; M.Z.Youssef*; M.A.Abdou*
Fusion Technology, 21(3), p.2190 - 2196, 1992/05
no abstracts in English
Watanabe, Tadashi; Kukita, Yutaka
Best Estimate Safety Analysis, p.1 - 7, 1992/00
no abstracts in English
Watanabe, Tadashi; Asahi, Yoshiro; *; Anoda, Yoshinari; *; Kukita, Yutaka
Proc. of the 1st JSME/ASME Joint Int. Conf. on Nuclear Engineering,Vol. 1, p.315 - 320, 1991/00
no abstracts in English
Araya, Fumimasa; ; Hirano, Masashi; *
EPRI-NP-6949, p.22-1 - 22-23, 1990/08
no abstracts in English
; Okumura, Keisuke; Takano, Hideki;
JAERI-M 90-109, 49 Pages, 1990/07
no abstracts in English
Nakakawa, Masayuki; Mori, Takamasa; Kosako, Kazuaki*; Oyama, Yukio; Nakamura, Tomoo
JAERI-M 89-154, 178 Pages, 1989/10
no abstracts in English
Araya, Fumimasa; ; Hirano, Masashi; Matsumoto, Kiyoshi; Yokobayashi, Masao; Kosaka, Atsuo
1989 Stability Symp., p.1 - 17, 1989/00
no abstracts in English
; ; *; ; ; *; ; Ono, Akio; ; *; et al.
JAERI-M 86-065, 126 Pages, 1986/03
no abstracts in English
; ; *; ; ; ; ; Ono, Akio; *; ; et al.
JAERI-M 85-045, 136 Pages, 1985/04
no abstracts in English
; ; *; *
JAERI-M 9473, 105 Pages, 1981/05
no abstracts in English
;
JAERI-M 5971, 13 Pages, 1975/02
no abstracts in English
Ishikawa, Makoto
no journal, ,
no abstracts in English
Numata, Kazuyuki*; Sugino, Kazuteru; Oki, Shigeo
no journal, ,
no abstracts in English
Matsuoka, Seikichi; Idomura, Yasuhiro; Honda, Mitsuru*; Satake, Shinsuke*; Suzuki, Yasuhiro*
no journal, ,
Effects of three-dimensional magnetic perturbation arising from e.g. error fields due to the imperfect coil manufacturing and installations, have attracted much attention in transport studies in axisymmetric tokamak plasmas. In this work, we performed global full-f gyrokinetic simulations for a JT-60U equilibrium which involve the three-dimensional perturbation by using experimental equilibrium version of a global full-f gyrokinetic simulation code, GT5D. Quantitative agreement of the neoclassical transport and the ambipolar radial electric field between GT5D and the existing couple analysis model is confirmed. And it is also confirmed that the neoclassical toroidal viscosity induced by the perturbation shows qualitative agreement with the couple analysis model. Furthermore, the numerical cost for the experimental analysis can be greatly reduced by using GT5D.
