Comparison of nuclear data of 64Cu production using an accelerator by TALYS 1.0 code

The extensive use of 64Cu (T1/2 = 12.7 h) as a positron and electron emitter radioisotope in recent years has ensured its potential to serve a dual role in the development of molecular agents in PET and radioimmunotheraphy drugs in oncology. The TALYS 1.0 code was used to calculate excitation functions for induced proton, deuteron and alfa-particles on 64Zn, 66Zn, 67Zn, 68Zn, 70Zn, 62Ni, and 64Ni up to 50 MeV. According to the data acquired by the TALYS 1.0 code, thick-target integral yield of the induced charged particles on the enriched targets was achieved

Neutronics investigation of CANada Deuterium Uranium 6 reactor fueled (transuranic–Th) O2 using a computational method

Background: 241Am, 243Am, and 237Np isotopes are among the most radiotoxic components of spent nuclear fuel. Recently, researchers have planned different incineration scenarios for the highly radiotoxic elements of nuclear waste in critical reactors. Computational methods are widely used to predict burnup rates of such nuclear wastes that are used under fuel matrixes in critical reactors. Methods: In this work, the Monte Carlo N-particle transport code was used to calculate the neutronic behavior of a transuranic (TRU)-bearing CANada Deuterium Uranium 6 reactor. Results: The computational data showed that the 1.0% TRU-containing thorium-based fuel matrix presents higher proliferation resistance and TRU depletion rate than the other investigated fuel Matrixes. The fuel matrix includes higher negative temperature reactivity coefficients as well. Conclusion: The investigated thorium-based fuel matrix can be successfully used to decrease the production of highly radiotoxic isotopes

Application of sulfonic acid functionalized nanoporous silica (SBA-Pr-SO3H) in the solvent free synthesis of (E)-arylidene-1,3-dihydroindole-2-ones

An efficient and green condensation reaction is developed for the synthesis of (E)-arylidene-1,3-dihydroindole-2-ones; (1), using heterogeneous nanoporous acid catalyst of SBA-Pr-SO3H with pore size, 6 nm in solvent free condition. Arylidene-1,3-dihydroindole-2-ones have many pharmaceutical properties such as Tyrosin kinase inhibiton. This method has the advantages of short reaction time, isolation ease of the products, excellent yields and recyclable catalyst

Burn-up calculation of different thorium-based fuel matrixes in a thermal research reactor using MCNPX 2.6 code

Decrease of the economically accessible uranium resources and the inherent proliferation resistance of thorium fuel motivate its application in nuclear power systems. Estimation of the nuclear reactor’s neutronic parameters during different operational situations is of key importance for the safe operation of nuclear reactors. In the present research, thorium oxide fuel burn-up calculations for a demonstrative model of a heavy water- -cooled reactor have been performed using MCNPX 2.6 code. Neutronic parameters for three different thorium fuel matrices loaded separately in the modelled thermal core have been investigated. 233U, 235U and 239Pu isotopes have been used as fissile element in the thorium oxide fuel, separately. Burn-up of three different fuels has been calculated at 1 MW constant power. 135X and 149Sm concentration variations have been studied in the modelled core during 165 days burn-up. Burn-up of thorium oxide enriched with 233U resulted in the least 149Sm and 135Xe productions and net fissile production of 233U after 165 days. The negative fuel, coolant and void reactivity of the used fuel assures safe operation of the modelled thermal core containing (233U-Th) O2 matrix. Furthermore, utilisation of thorium breeder fuel demonstrates several advantages, such as good neutronic economy, 233U production and less production of long-lived α emitter high radiotoxic wastes in biological internal exposure point of vie