Mixed nuclear fuel

A simulation-based study concerning three non-destructive approaches by which water in spent nuclear fuel assemblies might be quantified with neutrons is described. Three fuel types have been considered: thirty-six spent Advanced Gas-cooled Reactor (AGR) fuel pins contained in a stainless-steel can; a prototype fast reactor (PFR) spent fuel assembly and a light water reactor (LWR) spent fuel assembly – with the PFR and LWR assemblies containing mixed oxide fuels.

25p vironald 15-12-2022 13 4   Download

This paper presents the steady-state analysis results of the OECD/NEA and U.S. NRC PWR MOX/UO2 (MOX: Mixed Oxide) Core Transient Benchmark with the modern MCNP6 Monte Carlo code based on the ENDF/B-VII.1 evaluated nuclear data library.

10p meyerowitz 25-12-2021 8 0   Download

The study uses the data of the Philippines, Vietnam, and Thailand over the period of 1995-2017 as gathered from the World Bank and Global Economy. The study uses Brush Pagon LM and Pearson CD to test the cross-section dependence among variables while Levin et al., (2002) panel unit root test to check the stationary in the data. Westerlund (2007) cointegration and FMOLS tests are applied to analyze the long-run relationship.

8p nguaconbaynhay10 22-02-2021 12 4   Download

The main results of the research described are the following: (1) following the research on the influence of mixed fuel fission products (radioactive isotopes being formed during reactor operation as a result of nuclear decay of elements included into the fuel composition) on living organisms, the authors determined the quantities of plutonium dioxide (РuO2) that penetrated into blood and lay in the pulmonary region, liver, skeleton and other tissues.

11p minhxaminhyeu5 30-06-2019 20 1   Download

The article describes the results of experiments conducted on pigs to determine the effect of plutonium, which is the most radiotoxic and highly active element in the range of mixed fuel (U0.8Pu0.2)O2 fission products, on living organisms. The results will allow empirical prediction of the emergency plutonium radiation dose for various organs and tissues of humans in case of an accident in a reactor running on mixed fuel (U0.8Pu0.2)O2.

10p minhxaminhyeu5 30-06-2019 16 2   Download

In this research, we investigated the burnup characteristics and the conversion of fertile 232Th into fissile 233U in the core of a Sodium-Cooled Fast Reactor (SFR). The SFR fuel assemblies were designed for burning 232Th fuel (fuel pin 1) and 233U fuel (fuel pin 2) and include mixed minor actinide compositions. Monte Carlo simulations were performed using Serpent Code1.1.19 to compare with CRAM (Chebyshev Rational Approximation Method) and TTA (Transmutation Trajectory Analysis) method in the burnup calculation mode.

6p minhxaminhyeu5 30-06-2019 32 0   Download

In this study, we review previous stratified steam explosion experiments as well as recent experiments performed at the KTH in Sweden. While experiments with prototypic reactor materials are minimal, we do note that generally the energetics is limited for the stratified mode of contact. When the fuel mass involved in a steam explosion in a stratified geometry is compared to a pool geometry based on geometrical aspects, one can conclude that there is a very limited set of conditions

9p minhxaminhyeu3 12-06-2019 10 1   Download

The results show that the coolant void reactivity of the assembly analyzed in this paper is lower than that of 37-element bundle cell with natural uranium and 37-element bundle cell with mixed TU fuel pins; that the max time-average channel/bundle power of the core meets the limits - less than 6700kW/860 kW; that the fuel conversion ratio is higher than that of the CANDU-6 reactor with natural uranium; and that the exit burnup increases to 13400 MWd/tU.

7p minhxaminhyeu3 12-06-2019 5 0   Download

The wire-wrapped fuel bundle is an assembly design in a sodium-cooled fast reactor. A wire spacer is used to maintain a constant gap between rods and to enhance the mixing of coolants. The wire makes the flow complicated by creating a sweeping flow and vortex flow. The vortex affects the flow field and heat transfer inside the subchannels.

11p minhxaminhyeu3 12-06-2019 21 0   Download

The aim of this paper is to determine neutronic performances of the light water reactor (LWR) spent fuel mixed with fertile thorium fuel in a FFHR. Time dependent three dimensional calculations for major technical data, such as blanket energy multiplication, tritium breeding ratio, cumulative fissile fuel enrichment and burnup have been performed by using Monte Carlo Neutron-Particle Transport code MCNP5 1.4, coupled with a novel interface code MCNPAS.

10p minhxaminhyeu3 25-06-2019 19 0   Download

As the fastest growing source of energy in the world, wind has a very important role to play in the global energy mix. This becomes increasingly apparent as many countries begin to phase out traditional fossil fuels, while some re-evaluate their comfort level with nuclear power generation. The conversion of wind’s kinetic energy into another desired form dates back millennia. The years since have afforded some time for maturation of the technology.

0p ktcn_1 10-07-2012 110 17   Download