巻号一覧
27 巻, 8 号
選択された号の論文の9件中1～9を表示しています
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Kunihiko OKANO1990 年 27 巻 8 号 p. 689-699
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーThe recent successes in neutral beam current drive experiments on large tokamaks prompt us to consider the prospect of a beam driven steady state tokamak fusion reactor. A neoclassical theory on the beam driven current, which fully includes the toroidal effects on the induced ion and electron currents and is the most reliable to date, is reviewed in this article. The prospect of steady state tokamaks predicted by the theory may be somewhat pessimistic if the plasma current is sustained only by the beam driven current, because too much beam power is necessary for the current drive. However, thanks to the bootstrap current which was discovered in many tokamaks in recent years, the feasibility of a continuous tokamak operation will probably be highly improved because several tens of percent of the current will be produced by the bootstrap current. The energy gain Q would attain 30 to 50 in the power reactor and about 10 even for next generation (demonstration size) tokamaks.抄録全体を表示PDF形式でダウンロード (781K) -
Interpretation of Poles in Terms of Power Spectral DensitySumasu YAMADA, Kuniharu KISHIDA, Kenji SUMITA1990 年 27 巻 8 号 p. 700-711
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーSince the AR model widely used in the reactor noise analysis is mathematically a subset of the ARMA model, the characteristics of the AR model should be made clear for correct use of the resulting AR model. A simple tool called the PSD contour-map associated with the normalized PSD chart is proposed for interpretation and evaluation of the poles of the AR model from the viewpoint of the PSD. This tool not only visualizes the structure of the poles of the AR model but also provides us various information such as the importance of each pole of the AR model in the frequency region as well as the PSD difference of AR models with different model orders. The fundamental properties of the PSD of a pair of complex conjugate poles are extracted from the PSD contour-map in the form of rules. Model order reduction in AR model fitting is also discussed to show the effectiveness of the PSD contour-map.
It is also made clear in terms of the PSD that the information of the poles and zeros outside the convergence circle of the ARMA model is equivalently expressed in the AR model by relocation of the ring-poles representing the zero closest to the unit circle.抄録全体を表示PDF形式でダウンロード (802K) -
Akira URITANI, Chizuo MORI, Tamaki WATANABE, Akira MIYAHARA1990 年 27 巻 8 号 p. 712-717
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーA position sensitive 3He proportional counter for thermal neutrons with a novel signal readout method which has two pre-amplifiers at only one end of the counter body has been developed. It has an advantage for usage in a special environment, such as in a subcritical facility or in water, or for insertion into a narrow space. The characteristics of the counter were evaluated with thermal neutrons. The position resolution was 7 mm with an effective length of 1, 200 mm. The integral non-linearity of position signal was less than 0.5%.抄録全体を表示PDF形式でダウンロード (454K) -
Tomoyuki MATSUMOTO, Yoshihiko ISHII1990 年 27 巻 8 号 p. 718-730
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーA multi-channel thermal hydraulic model for LOCA analysis of a heterogeneous core such as a HCBWR has been developed. This model solves integral formulations for basic equations based on a one-dimensional drift flux model. The core region is divided into several fuel channel groups which differ in their thermal power or geometry. The various flow patterns in the core are determined by calculating the redistribution of vapor generated in the lower plenum into the fuel channel groups. In order to verify the multi-channel model, a computer program FLORA was developed based on the multi-channel model and large and small break LOCA experiments conducted in the Two Bundle Loop (TBL) facility were analyzed by the FLORA program. As a result, the difference in thermal hydraulic behavior between two bundles with different power in the various break LOCA experiments were well simulated.抄録全体を表示PDF形式でダウンロード (895K) -
Impurity Ions Balance Evaluation Based on Conductivity Data and Its Application to Water Chemistry Diagnosis in BWR PlantsYamato ASAKURA, Makoto NAGASE, Shunsuke UCHIDA, Katsumi OHSUMI, Hiroo ...1990 年 27 巻 8 号 p. 731-742
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーA water chemistry diagnosis model was developed which quantitatively evaluates ionic impurity behavior in case of equipment nonconformity or operating condition change by analyzing the conductivity change along with the coolant flow in the primary cooling system in BWRs. The model propriety was evaluated using water chemistry data of the Tokai-2 plant.
In the case of a sea water in-leak at the main condenser, the sea water in-leak flow rate of 3l/h was the lower detection limit when searching for the leakage location in a condenser tube so as to repair it. The prediction trend of the reactor water conductivity agreed with the measured one within ±10% error in the case of the CUW flow rate transient. The conductivity increase in the reactor obtained by conductivity balance evaluation was approximately found to correspond to the small chromate ion release rate from structural materials and it could be put to practical use as an index to understand the generation behavior of ionic impurity in the reactor.抄録全体を表示PDF形式でダウンロード (678K) -
Isao YAMAGISHI, Masumitsu KUBOTA1990 年 27 巻 8 号 p. 743-749
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーThe desorption behavior of Tc from active carbon was studied as a fundamental study on separating Tc from high-level radioactive liquid waste. Technetium adsorbed from 0.5 M HNO3 solution could be desorbed more effectively with alkaline thiocyanate solution than with HNO3. The adsorption behavior of Tc on the active carbon previously treated with alkaline thiocyanate solution was also studied for the purpose of a recycle use of the active carbon.
The distribution coefficient of Tc, Kd, depended sensitively on pH in the presence of KSCN. The value of Kd exceeded 105 ml/g below pH 2 and became less than 10 ml/g above pH 4. It was found by spectrophotometric analysis that this large difference in Kd was due to the change of the chemical form of Tc. Below pH 2, Tc was adsorbed in the form of thiocyanate complexes, [Tc(NCS)6]2- and [Tc(NCS)6]3-. Above pH 4, these complexes were hardly formed and TcO4- was desorbed by anion exchange reaction with thiocyanate ion.抄録全体を表示PDF形式でダウンロード (477K) -
Difference of Migration Behavior and Desorption Process for RadionuclidesYoshiro OHTSUKA, Shinichi TAKEBE1990 年 27 巻 8 号 p. 750-755
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーDifferences of the migration behavior and desorption process for radionuclides (60Co, 85Sr and 137Cs) in aerated sandy soil layer were studied by sprinkle of distilled water into the contaminated soil with above nuclides in column. Influence of difference desorption process on radionuclide migration was examined by changing the volume of distilled water sprinkled like rain on the contaminated soil.
Quantity of sprinkled water affected the concentration distribution of each radionuclide in soil layer. Each nuclide migrated deeper in the layer according to the increase of water amount, and especially, migration behavior of 85Sr was remarkably influenced by water amount. It is observed that as to 85Sr maximum contamination part in soil layer moved to deeper layer with increase of water amount, and that, as to 60Co and 137Cs, it moved almost never. On the other hand, activity concentration of 60Co or 137Cs in effluent was rather high (10-6 μCi/ml) compared with that of 85Sr, which could not be detected therein.抄録全体を表示PDF形式でダウンロード (386K) -
LIU Ting-jin, Keiichi SHIBATA, Tsuneo NAKAGAWA1990 年 27 巻 8 号 p. 756-765
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーNeutron nuclear data of natural silver and its isotopes (107Ag and 109Ag) have been evaluated in the energy range of 10-5 eV20 MeV. Evaluated quantities are the total, elastic and inelastic scattering, capture, (n, 2n), (n, 3n), (n, p), (n, α), (n, np), (n, nα) reaction and γ-ray production cross sections, the resonance parameters and the angular and energy distributions of emitted neutrons and γ-rays. The evaluation is based on available experimental data and theoretical calculations. Multi-step Hauser-Feshbach calculation played an important role in the determination of the reaction cross sections. In the calculation, the precompound process was taken into account above 5 MeV, in addition to the compound one. The evaluated data have been compiled into JENDL-3 in the ENDF-5 format.抄録全体を表示PDF形式でダウンロード (609K) -
A TRKOV, M NAJZER, L SKERGET1990 年 27 巻 8 号 p. 766-777
発行日: 1990/08/25
公開日: 2008/05/14
ジャーナル フリーA variant of the Green's function nodal method derived from the boundary integral form of the multigroup neutron diffusion equation in rectangular geometry is presented. As usual in the nodal methods, the multi-dimensional diffusion equation is integrated in the transverse direction. The resulting 1D diffusion equation is solved following the Boundary Element technique in one dimension. In this way a weighted residual method is obtained, with a Green's function for weighting, but with different boundary conditions than normally applied in the Green's function nodal methods. Mathematical formulation of the method is given and the iteration procedure is described. A computer program BINDIF has been designed, based on the new method. Its capabilities include the solution of the multigroup neutron diffusion equation of 1D, 2D and 3D rectangular lattices. The BINDIF program has been checked against other methods used for global reactor calculations on benchmark problems, representative of realistic power reactor cores. The results indicate that the method is attractive to design highly efficient algorithms for a large mainframe, a personal computer or a parallel processor.抄録全体を表示PDF形式でダウンロード (863K)
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