Computer Simulation and Field Experiment for Downlink Multiuser MIMO in Mobile WiMAX System.

The transmission performance for a downlink mobile WiMAX system with multiuser multiple-input multiple-output (MU-MIMO) systems in a computer simulation and field experiment is described. In computer simulation, a MU-MIMO transmission system can be realized by using the block diagonalization (BD) algorithm, and each user can receive signals without any signal interference from other users. The bit error rate (BER) performance and channel capacity in accordance with modulation schemes and the number of streams were simulated in a spatially correlated multipath fading environment. Furthermore, we propose a method for evaluating the transmission performance for this downlink mobile WiMAX system in this environment by using the computer simulation. In the field experiment, the received power and downlink throughput in the UDP layer were measured on an experimental mobile WiMAX system developed in Azumino City in Japan. In comparison with the simulated and experimented results, the measured maximum throughput performance in the downlink had almost the same performance as the simulated throughput. It was confirmed that the experimental mobile WiMAX system for MU-MIMO transmission successfully increased the total channel capacity of the system.

Two-dimensional differential calibration method for a neutron dosemeter using a thermal neutron beam.

A new thermal neutron calibration method to experimentally determine the energy response function of a neutron detector using a pulse parallel beam and the time-of-flight (TOF) technique is developed. The calibration method was experimentally demonstrated for a (3)He proportional counter and an electric personal dosemeter using a pulsed thermal neutron beam from the research reactor JRR-3M. The responses of the detectors were successfully obtained as a function of neutron energy. However, detailed information on the detector structure is required to obtain the spatial response distribution for the detector. The authors further propose an improved calibration method obtaining the spatial response distribution using a pulsed narrow beam, the TOF technique and a beam scanning technique.

Sensitivity variation for H, B, Si, Cl, Ca and Cd in solid materials by prompt gamma-ray analysis with a special emphasis on the presence of hydrogen.

The effects of neutron scattering by matrix hydrogen in geological samples were examined in order to accurately determine their chemical compositions by neutron-induced prompt gamma-ray analysis (PGA). Three different matrix materials including basaltic reference rock sample (JB-2) mixed with chemical reagents including H-containing ones were analyzed by using thermal and/or cold neutron-guided beams of JRR-3 at Japan Atomic Energy Agency. The sensitivity change of elements with the variation of the H concentrations was evaluated for disk and spherical target geometries. The results show that the analytical sensitivities of B, Cl and Cd in disk samples seem to increase with increasing the matrix H concentrations by the irradiation of both thermal and cold-neutron beams. The sensitivity enhancement of B for disk-shaped JB-2 mixed with up to 2% mass H is within the analytical uncertainty associated with PGA with a thermal-neutron beam.

Carbon-14 analysis in solidified product of non-metallic solid waste by a combination of alkaline fusion and gaseous CO2 trapping.

In order to establish a simple and rapid analytical method for (14)C in solidified products made from non-metallic low-level radioactive solid wastes such as concrete, mortar and glass by melting treatment, a radiochemical analysis in combination with alkaline fusion as a sample decomposition method was examined. A simulated solidified product containing (14)C, which was prepared by using nuclear reaction (14)N(n, p)(14)C with thermal neutron irradiation, was analyzed by the present method to compare with a conventional radiochemical analysis using oxidizing combustion. The reproducible and quantitative recovery of (14)C from the simulated solidified product indicates that the present method is more efficient for (14)C analysis in solidified products than the conventional method using oxidizing combustion.

Accurate determination of arsenic in arsenobetaine standard solutions of BCR-626 and NMIJ CRM 7901-a by neutron activation analysis coupled with internal standard method.

Neutron activation analysis (NAA) coupled with an internal standard method was applied for the determination of As in the certified reference material (CRM) of arsenobetaine (AB) standard solutions to verify their certified values. Gold was used as an internal standard to compensate for the difference of the neutron exposure in an irradiation capsule and to improve the sample-to-sample repeatability. Application of the internal standard method significantly improved linearity of the calibration curve up to 1 microg of As, too. The analytical reliability of the proposed method was evaluated by k(0)-standardization NAA. The analytical results of As in AB standard solutions of BCR-626 and NMIJ CRM 7901-a were (499+/-55)mgkg(-1) (k=2) and (10.16+/-0.15)mgkg(-1) (k=2), respectively. These values were found to be 15-20% higher than the certified values. The between-bottle variation of BCR-626 was much larger than the expanded uncertainty of the certified value, although that of NMIJ CRM 7901-a was almost negligible.

Precise determination of Cr and Co in certified reference material of silicon nitride by neutron activation analysis using internal standardization.

Neutron activation analysis with an internal standard correction was applied to the determination of Cr and Co in a ceramics certified reference material (NMIJ CRM 8004-a silicon nitride powder). Cesium was used as an internal standard to compensate for any inhomogeneity of the neutron flux through an irradiation capsule and to improve the repeatability of gamma-ray measurements. It was found that the linearity of the calibration curves of Cr and Co was improved by using an internal standard. The analytical results of Cr and Co in NMIJ CRM 8004-a were in good agreement with those obtained by ICP-OES, ICP-sector field mass spectrometry (ICP-SFMS), and isotope dilution/ICP-SFMS for Cr. The relative expanded uncertainties (k = 2) were 1.9% for Cr and 1.5% for Co. The uncertainties were comparable to those of atomic spectrometric methods.