Analytical Method of Atomic Density Determination of Uranyl Nitrate Solution
Creators
- 1. Centre for Science & Accelerator Technology, JL. Babarsari, POB 6101 ykbb, Yogyakarta 55281, Indonesia. (Indonesia)
Description
A basic theory of an analytical calculation method to determine the atomic density of each individual nuclide contained in a homogeneous system of uranyl nitrate solution is presented. Atomic density or number density is a number of atoms or nuclides per cm3 or in a unit of atoms per barn-cm. This parameter is one of the important factors in defining the accuracy of neutronic calculations as such used in reactor core design. This work was carried out as part of neutronic design calculation of the SAMOP (subcritical assembly for 99Mo isotope production) project, where uranyl nitrate solution was used as fuel with uranium enrichment of 20%. A homogeneous solution made by dissolving uranyl nitrate salt [UO2 (NO3)2] into H2O solvent has been used as an approach to this model. Two kinds of solution were described i.e. one that was made based on the amount of UO2(NO3)2 dissolved in the solution and another one based on the amount of uranium in the solution. Expectedly this method can be used as an alternative way in estimating the atom density, solution density (g/cc) and the corresponding atom and weight fractions which is important in criticality calculations. (paper)
Availability note (English)
Available from http://dx.doi.org/10.1088/1742-6596/1090/1/012036Additional details
Identifiers
Publishing Information
- Journal Title
- Journal of Physics. Conference Series (Online)
- Journal Volume
- 1090
- Journal Issue
- 1
- Journal Page Range
- [9 p.]
- ISSN
- 1742-6596
Conference
- Title
- International Conference on Computation in Science and Engineering
- Dates
- 10-12 Jul 2017
- Place
- Bandung (Indonesia)
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53023670
- Subject category
- S11: NUCLEAR FUEL CYCLE AND FUEL MATERIALS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CALCULATION METHODS; CRITICALITY; DENSITY; ISOTOPE PRODUCTION; ISOTOPE SEPARATION; MOLYBDENUM 99; NITROGEN OXIDES; NUCLEAR FUELS; REACTOR CORES; REACTOR DESIGN; SOLUTIONS; SOLVENTS; SUBCRITICAL ASSEMBLIES; URANIUM; URANIUM DIOXIDE; URANYL NITRATES
- Descriptors DEC
- ACTINIDE COMPOUNDS; ACTINIDES; BETA DECAY RADIOISOTOPES; BETA-MINUS DECAY RADIOISOTOPES; CHALCOGENIDES; DAYS LIVING RADIOISOTOPES; DESIGN; DISPERSIONS; ELEMENTS; ENERGY SOURCES; EVEN-ODD NUCLEI; EXPERIMENTAL REACTORS; FUELS; HOMOGENEOUS MIXTURES; INTERMEDIATE MASS NUCLEI; ISOTOPES; MATERIALS; METALS; MIXTURES; MOLYBDENUM ISOTOPES; NITRATES; NITROGEN COMPOUNDS; NUCLEI; OXIDES; OXYGEN COMPOUNDS; PHYSICAL PROPERTIES; RADIOISOTOPES; REACTOR COMPONENTS; REACTOR LIFE CYCLE; REACTOR MATERIALS; REACTORS; RESEARCH AND TEST REACTORS; SEPARATION PROCESSES; URANIUM COMPOUNDS; URANIUM OXIDES; URANYL COMPOUNDS