Time filter

Source Type

Nakamura T.,Kyushu University | Vo Doan H.D.,Dalat Nuclear Research Institute | Kotoh K.,Kyushu University
Energy Procedia

We have considered a fuel cycle scheme for multi-recycling of plutonium recovered from spent UO2 fuels of LWRs. Plutonium is to be partially loaded into the next LWRs in the form of MOX fuels with UO2 fuels made by re-enrichment of uranium recovered from spent fuels of LWRs. We consider to recycle plutonium in combination with uranium multi-recycling system previously reported, which can provide uranium fuels for not only fully UO 2 fueled PWRs but also partially MOX fueled PWRs. The results of the process system analysis suggest that the proposed scheme makes it possible to recycle plutonium in succession. © 2013 The Authors. Source

Tan V.H.,Agency for Radiation and Nuclear Safety | Son P.N.,Dalat Nuclear Research Institute
Journal of Physics: Conference Series

The thermal neutron radiative capture cross section for186W(n, γ)187W reaction was measured by the activation method using the filtered neutron beam at the Dalat research reactor. An optimal composition of Si and Bi, in single crystal form, has been used as neutron filters to create the high-purity filtered neutron beam with Cadmium ratio of Rcd = 420 and peak energy En = 0.025 eV. The induced activities in the irradiated samples were measured by a high resolution HPGe digital gamma-ray spectrometer. The present result of cross section has been determined relatively to the reference value of the standard reaction197Au(n, γ)198Au. The necessary correction factors for gamma-ray true coincidence summing, and thermal neutron self-shielding effects were taken into account in this experiment by Monte Carlo simulations. © Published under licence by IOP Publishing Ltd. Source

Hieu T.Q.,Ho Chi Minh City University of Technology | Tuan N.N.,Dalat Nuclear Research Institute | Van Tan L.,Ho Chi Minh City Industrial University
Asian Journal of Chemistry

The work describes a new 1:1 complex of o-ester tetra azophenyl calix[4]arene (TEAC) with Th(IV) at pH 4-5 has found. The FTIR, H NMR, Raman spectra of calix[4]arene and its Th(IV) complex had also checked. Based on complex formation, a new method has been developed to determine thorium in monazite sand. The sand samples are decomposed by mixed acid (conc. H2SO4 and HF) in platinum crucible, after cooling, the residue was dissolved in dilute HCl and thorium is separated together with the lanthanides in the form of oxalate from zirconium, iron and the phosphate ion. The oxalate precipitate is dissolved in concentration nitric acid. After that, Th(IV) will be formed complex with o-ester tetra azophenyl calix[4]arene in acetate buffer solution. The absorbance of complex solution was measured at 520 nm against water as blank. Source

Son P.N.,Dalat Nuclear Research Institute | Anh T.T.,Dalat Nuclear Research Institute | Vu C.D.,Dalat Nuclear Research Institute | Tan V.H.,Vietnam Atomic Energy Institute
Journal of the Korean Physical Society

Thermal neutron capture cross-sections and resonance integrals for 69Ga and 71Ga were measured by the activation method. The experimental samples with and without a cylindrical Cd-shield case 1 mm in thickness were irradiated in the neutron field of the thermal column facility of Dalat research reactor. The induced activities in the samples were measured by using a high-resolution HPGe detector. Thermal neutron cross-sections for 2200 m/s neutrons and resonance integrals for the 69Ga(n,γ)70Ga and 71Ga(n,γ)72Ga reactions have been obtained relative to the reference values of the 197Au(n,γ)198Au reaction with σ0 = 98.65 ± 0.09 barn and I0 = 1550 ± 28 barn. The necessary correction factors for thermal neutron and resonance neutron self-shielding effects were taken into account in the determinations. The present results are discussed and compared with the evaluated data from ENDF/BVII, JEFF 3.0 and JENDL 3.3. Source

Son P.N.,Dalat Nuclear Research Institute | Hai N.X.,Dalat Nuclear Research Institute
Journal of Physics: Conference Series

Precise information on the decay heat from fission products following times after a fission reaction is necessary for safety designs and operations of nuclear-power reactors, fuel storage, transport flasks, and for spent fuel management and processing. In this study, the timing distributions of fission products' concentrations and their integrated decay heat as function of time following a fast neutron fission reaction of232Th were exactly calculated by the numerical method with using the DHP code. © Published under licence by IOP Publishing Ltd. Source

Discover hidden collaborations