Reinforced concrete beams as structural elements that are often found are elements that are quite large in their role in bearing loads. Judging from the function of support as a bearer of tensile force, it is possible if the reinforced concrete beams are made with different numbers and areas of reinforcement. Reinforcement bundles are used if there is a cross-sectional dimension limitation without the distance between the reinforcement conditions being met. Beams with 2 reinforcement bundles are made to see the flexural capacity obtained. With the dimensions of the beam 150 mm x 200 mm x 1050 mm, a bundle of 2 reinforcement with a diameter of 10 mm is mounted on the tensile section of reinforced concrete beams. With a four-point bending test, a nominal bending moment is obtained. Single-section square cross-section analysis with cross-sectional area obtained using the equivalent diameter of the reinforcement bundle compared to the flexural test results. The bending moment capacity between experiment and analysis obtained the appropriate results. The bending capacity value of the two reinforcement bundles is still large so that the bending failure has not been reached.

Characterization neutron and gamma beams at the tangential beam port of TRIGA 2000 reactor was done in order to prepare the development of Prompt Gamma Neutron Activation Analysis (PGNAA) facility. Characterization was performed by simulation using Monte Carlo method with MCNPX and PHITS computer codes. The MCNPX code was used to simulate the neutron-gamma fluence and energy spectra in the reactor core from fission reactions. The PHITS code was used to simulate the distribution of the neutron-gamma fluence and energy spectra in the tangential beam port. The simulation was done by modeling the geometry and elemental composition of reactor material and radiation source model in the form of fission reaction in the reactor core. The results indicate that the tangential beam port provides better neutron spectrum and neutron-gamma fluence ratio for PGNAA. These results will be used to simulate the colimator design and neutron interaction with samples in PGNAA facility.

The BNCT in-vitro test using a microtube irradiated in the neutron beam of the RSG-GAS beam tubes has been simulated using PHITS code. The simulation was performed by modeling a microtube containing boron solution which was placed 5 cm in front of the beam tubes. Inside the beam tube was installed a beam shaping assembly (BSA) using 80 cm of MgF 2 as a filter to reduce fast neutron and gamma fluences. Microtube containing 1.5 mL of boron solution with boron enriched 10B of 90%. The microtube dose i.e alpha dose, 7Li dose, proton dose, and gamma dose were calculated for boron concentration of 1 ppm. The simulation of microtube containing 1 ppm boron solution shown that irradiated in the BSA-S5 neutron beam can produce 20 Gy dose in the shortest irradiation time of 2.5 hours.