In the water cooled blanket of fusion experimental facility there are many parallel flow channels for heat transfer. Especially in the first wall the parallel rectangular flow channels face very high heat flux. The flow channel may become narrow due to long-term impurity deposition or channel deformation. This phenomenon will influence the heat transfer performance and sometimes even cause accident

The use of zirconium hydride in fast reactors provides excellent MA transmutation performance by neutron moderation with hydrogen. This study has designed an MA transmutation fast reactor loading a ‘target” containing MA-zirconium hydride in the blanket fuel region to maximize the transmutation capability of the core. As the result, the three-region core of the small fast reactor has been designed

Present electric grids are advanced to integrate smart grids, distributed resources, high-speed sensing and control, and other advanced metering technologies. Cybersecurity is one of the challenges of the smart grid and nuclear plant digital system. It affects the advanced Metering Infrastructure (AMI), for grid data communication and controls the information in real-time. The research article is emphasized

As a burnable absorber, gadolinium oxide (Gd2O3) is widely used in light water reactors due to the high neutron absorption cross section of several gadolinium isotopes and its good solid solubility in UO2. However, some isotopes of natural Gd cause residual reactivity suppression, while some are not efficient neutron absorbers, reducing the efficiency of the burnable absorber when implemented. In this

Abstract USNC-Technologies (USNC-Tech) is an advanced nuclear company focused on developing space nuclear power and propulsion systems to enable high-impact science missions and the growth of a self-sustaining in-space economy. As a subsidiary of Ultra Safe Nuclear Corporation (USNC), USNC-Tech has leveraged the technologies and experience gains from the design, licensing, and deployment of terrestrial

We derive the nucleon-nucleon interaction from the Skyrme model using second order perturbation theory and the dipole approximation to skyrmion dynamics. Unlike previous derivations, our derivation accounts for the non-trivial kinetic and potential parts of the skyrmion-skyrmion interaction lagrangian and how they couple in the quantum calculation. We derive the eight low energy interaction potentials

Excitation functions for the natTi(3He, x)44g,mSc nuclear reactions were measured from respective threshold up to 55 MeV by using a conventional stacked-foil activation technique combined with HPGe γ-ray spectroscopy. Individual cross-section values for the production of 44mSc and 44gSc were separated using a proper mathematical method on the basis of their individual gamma lines and the data for 44gSc

The oxidized residual strength for two nuclear graphite grades, fine-grained IG-110 and medium-grained NBG-18, were determined over a mass loss range of 0% to 10% for three different oxidation temperatures. This study addresses the critical licensing issue of determining oxidized strength of graphite core components within the design rules of the American Society of Mechanical Engineers (ASME) Boiler

KYLIN-V2.0 is an advanced neutron transport lattice physics code developed by the Nuclear Power Institute of China (NPIC). This paper presents a brief introduction of the methodology used in the KYLIN-V2.0 code, and focuses on the verification of KYLIN-V2.0. In this paper, various fuel pin, fuel assembly models in the VERA, JAEA, and BEAVRS benchmark have been built by KYLIN-V2.0 code to verify its

Molten salt reactors (MSRs) are being investigated as a possible source of 99Mo for medical uses. This paper describes computational modeling being performed to determine the feasibility for use of several MSR concepts in 99Mo production: the Molten Salt Breeder Reactor (MSBR), the Molten Salt Demonstration Reactor (MSDR), and the Molten Salt Reactor Experiment (MSRE). This modeling is accomplished

NHR200-Ⅱ is a 200 MW nuclear heating reactor. The integrity of the fuel assembly should be ensured during the normal operations and design basis accidents. In the latter cases (e.g. earthquake), its deformation or damage should not prevent the insertion of control rods to shut down the reactor. Meanwhile, during the operating time, there are two aspects that attention should be paid, (i) the mechanical

The pressure vessel has used a newly designed water seal structure, and the sealed water is from condensation at low hydrogen concentration. To get the condensation capacity of the water seal branch tube under the pressure vessel normal operation, the experimental loop named WASETEL was constructed, which is aimed at studying the heat transfer during the process of air-steam mixture condensation inside

This paper introduces the experimental method of using mass transfer systems for heat transfer studies based on the analogy between heat and mass transfer. The copper electroplating system, composed of copper electrodes submerged in an aqueous solution of H2SO4 and CuSO4, is employed as the mass transfer system. The cupric ions transferred from anode to cathode simulate heat transfer. Applications

The Accident Source Term Evaluation Code (ASTEC) and Methods of Estimation of Leakages and Consequences of Releases (MELCOR) system codes are used in Tractebel to perform source term assessments and plant Thermal Hydraulic (TH) analyses in case of Severe Accident (SA) for the Belgian Nuclear Power Plants (NPPs). These system codes were developed through intense and extensive validation activities which

The Rare Isotope Science Project was launched in 2011 in Korea toward constructing the Rare isotope Accelerator complex for ON line experiments (RAON). RAON will house several experimental systems, including the Muon Spin Rotation/Relaxation/Resonance (μSR) facility in High Energy Experimental Building B. This facility will use 600-MeV protons with a maximum current of 660 pμA and beam power of 400

This work deals with the validation of a high-fidelity multiphysics system coupling the Serpent 2 Monte Carlo neutron transport code with SUBCHANFLOW, a subchannel thermalhydraulics code, and TRANSURANUS, a fuel-performance analysis code. The results for a full-core pin-by-pin burnup calculation for the ninth operating cycle of the Temelín II VVER-1000 plant, which starts from a fresh core, are presented

Traditional reactor system analysis tools are confronted with challenging difficulties in model development, low accuracy, and poor convergence. To solve these problems, the automatic differentiation (AD) method that allows the automatic numerical calculation of derivatives of functions was adopted to develop the reactor system code in this paper. For the simulation of single-phase models, the steady

Transition from conventional analog technology to advanced digital technology is a global trend, and commercial and research reactors are increasingly using digital instrumentation and control (I&C) systems. However, common cause failures (CCFs) of the digital platform are significant issues. In this paper, we proposed a potential solution for such CCFs by implementing a digital hybrid model that combines

In the online fission gas removal system applied to TMSR, the venturi bubble generator was developed to produce the dispersed bubbles from the reactor coolant. It is essential to establish the critical condition of bubble breakup for the bubble generation. Numerical simulations of the bubble dynamics in an unsteady turbulent flow in the bubble generator are performed with Volume-of-fluid (VOF) and

The production of heavy-mass elements due to the rapid neutron-capture mechanism (r-process) is associated with astrophysical scenarios, such as supernovae and neutron-star mergers. In the r-process the capture of neutrons is followed by β-decays until nuclear stability is reached. A key element in the chain of nuclear weak-decays leading to the production of isotopes may be the change of the parameters

We review the current understanding of time-like virtual photon emission from QCD matter. The phenomenology of dilepton emission is discussed and basic theoretical concepts are introduced. The experimental findings are presented, grouped into production of lepton pairs in elementary processes, production off cold nuclear matter and emission from heavy-ion collisions. The review emphasizes the role

Mo–3Nb single crystal is an important material used for processing the emitter of space thermionic reactor. The present research focuses on the microstructures of precipitated phases in the Mo–3Nb matrix and the joint welded by the vacuum electron beam, to reveal the microstructural transformation during the welding process. Characterization of the precipitates was conducted by transmission electron

Abstract Nuclear thermal propulsion (NTP) provides a consistent source of thrust for long space missions. However, fuel development for NTP reactors is a major technological hurdle. Existing modeling and simulation tools developed by the U.S. Nuclear Engineering Advanced Modeling and Simulation (NEAMS) program for power reactors can be leveraged to help accelerate the fuel development. This work is

Abstract In this study, lattice physics calculations were carried out to evaluate the reactor physics characteristics of different advanced fuel lattices cooled with 7LiOH/NaOH or FLiBe and moderated externally by graphite and various types of metal hydroxides, such as 7LiOH, 7LiOD, Mg(OD)2, and ZrE(OD)4. The lithium in these compounds is enriched to 99.995 at. % 7Li/Li. Such lattice fuel concepts

Abstract Post Fukushima the U.S. Nuclear Regulatory Commission issued an Order on Spent Fuel Instrumentation (EA-12-051) requiring all U.S. nuclear plants to install spent fuel pool (SFP) water level monitoring instrumentation and ensure the instrument would remain functional following a safe shutdown earthquake (SSE). The structural integrity analysis requires an assessment of the hydrodynamic loads

Abstract Natural circulation, mixing, and stratification are important phenomena for the design and safety analysis of many advanced reactor designs with passive safety features as well as large open regions, such as pool reactor designs, spent fuel pools, and containments. Various modeling methods ranging from zero-dimensional (0-D) lumped volumes (or perfect mixing) to full three-dimensional (3-D)

The lepton universality violating flavor ratios RK/RK⁎ indicate new physics either in b→sμ+μ− or in b→se+e− or in both. If the new physics is only b→se+e− transition, the corresponding new physics operators, in principle, can have any Lorentz structure. In this work, we perform a model independent analysis of new physics only in b→se+e− decay by considering effective operators either one at a time

We compute the non-planar contribution to the universal anomalous dimension of twist-two operators in N=4 supersymmetric Yang-Mills theory at four loops through Lorentz spin eighteen. Exploiting the results of this and our previous calculations along with recent analytic results for the cusp anomalous dimension and some expected analytic properties, we reconstruct a general expression valid for arbitrary

In this study, latent and etched ion tracks generated by high electronic excitation in alpha quartz (α-SiO2) were characterized. Single crystals of Y- and Z-cut α-SiO2 were irradiated at room temperature with 20 MeV Ni6+ ions and 40 MeV I7+ ions. The track morphology depends on the energy of the incident ion and the stopping power on the target material. Subsequent chemical vapor-etching with hydrofluoric

A pulsed system capable of delivering up to a few microamps with a mass range 1–100 u, and with pulse width of bursts of ions approximately 1–2 ns is described. Critical design limitations are discussed to show the overall approach to meet a number of experimental requirements. The system consists of a SNICS negative ion source, a low energy buncher which uses the entire tandem electrostatic accelerator

Abstract High heat flux components form the primary interface for thermal management of injectors in fusion devices. The requirement for such application varies from 1 to 10 MW/m2. Ultra-high-vacuum compatibility is the inherent characteristic of such components, and manufacturing processes involve the development of specific materials, process qualification of special processes like electron beam

A Monte-Carlo method for the generation of correlation and covariance matrices for independent and cumulative fission yields has been developed. The method uses a constrained Monte-Carlo resampling structure in order to vary evaluated fission yield libraries in a way that meets basic conservation principles. This results in the generation of correlation/covariance matrices with limited model bias and

The root-mean-square (rms) charge radii of 236 nuclides measured by laser spectroscopy experiment are compiled, and the uncertainties are calculated. From the rms charge radii of Mg isotope chain, the new magic number N=14 can be observed, and the traditional magic number N=20 disappears in the K isotope chain. A good linear relationship between the difference of the mirror nuclear charge radii and

Copper is an important structural material in various nuclear energy applications, therefore the correct knowledge of copper cross sections is crucial. The presented paper deals with a validation of different copper transport libraries by means of activation of selected samples. An intense 252Cf(sf) source with a reference neutron spectrum was used as a neutron source. After irradiation, the samples

Dynamic seals are one of the critical components of Absorber Rod Drive Mechanism of Fast Breeder Reactors, requiring separate experimental development. Their significance can’t be overemphasized considering that the availability and re-usability of Control Rod Drive Mechanisms of Fast Breeder Test Reactor is governed by the failure rate of dynamic seals (bellows). For prototype and subsequent Fast

ABSTRACT The pressure control in the pressurized water reactor (PWR) primary loop is key to secure the safe operation. The pressurizer (PZR) unit is responsible for attaining this task. Thus, the PZR unit’s modeling is an important issue for the tracking control purpose and performance analysis concerning the turbine load. This paper develops a mathematical model to accurately predict the PZR unit

With the development of nuclear industry, spent nuclear fuel (SNF) generated from nuclear power plants arouses people’s attention as a result of its high radioactivity, and how to guarantee the reliable operation of nuclear facilities and the staff’s safety occupies a crucial position. To avoid the lethal irradiation, a lot of functional neutron shielding composites have been developed to transform

A short-term station blackout (STSBO) accident has been considered as one of risk dominant sequences for nuclear power plants (NPPs). Unless appropriate mitigation actions are not taken, a rapid damage of the reactor core and thereby a severe accident may result in. This paper presents best practice analysis results on the evolution of the severe accident sequences and fission product (FP) source terms

As the share of renewable energy will be increasing, there is a growing interest in flexible power sources and energy storage systems due to the intermittent nature of renewable energy. We propose the Energy Storage System (ESS) integrated Nuclear Power Plant (NPP) as a solution. The system operates on load-following by branching the mass flow from the steam cycle to the ESS without changing the reactor

The corrosion results in not only material degradation but also causes CRUD generation in the primary coolant. The axial offset anomaly (AOA) or CRUD Induce Power Shift (CIPS) is caused by CRUD accumulation on the fuel assemblies. It also causes an increase in Occupational Radiation Exposure (ORE). Therefore, in this work, activated CRUD behavior due to 54Mn, 59Fe, 58Co, 60Co, and 51Cr has been studied

At radioactive waste disposal facilities all around the world, radiation shielding is required to reduce the background γ-radiation as much as possible in order to achieve protection against high radiation. In the current study, an inexpensive material, Portland cement, has been utilized as shielding material against γ-radiation from radioactive materials including radioactive wastes. Portland cement

The characterization of the radiation shielding properties of a fired lead ore deposit (LOD) found in Enyigba, Ebonyi state have been investigated experimentally and by XCOM calculation. The electric kiln furnace purification technique and the Atomic Absorption Spectroscopy (AAS) were used in establishing the lead content in the ore, while the X - ray transmission measurement at peak voltages of 100 kVp

In this brief review, we present the results of the fractional differential approach in cosmology in the context of the exact models of cosmological accelerated expansion obtained by several authors to date. Most of these studies are devoted to the problem of introducing fractional derivatives or fractional integrals into the classical General Relativity (GR). There are several observational and theoretical

The status of multifractional theories is reviewed using comparative tables. Theoretical foundations, classical matter and gravity dynamics, cosmology and experimental constraints are summarized and the application of the multifractional paradigm to quantum gravity is discussed. We also clarify the issue of unitarity in theories with integer-order derivatives.

We construct a tensor-matrix model which describes 3-dimensional (3D) Causal Dynamical Triangulation (CDT) of open-closed surface. Though the usual splitting interaction of a surface is not derived from the stochastic quantization procedure, it provides another interaction of IK-type, which becomes the sole quantum correction. Through the double scaling limit, it realizes CDT open-closed surface field

In the present paper we develop the algebraic Bethe ansatz approach to the case of non-skew-symmetric gl(2)⊗gl(2)-valued Cartan-non-invariant classical r-matrices with spectral parameters. We consider the two families of these r-matrices, namely, the two non-standard rational r-matrices twisted with the help of second order automorphisms and realize the algebraic Bethe ansatz method for them. We study

Using the BRST approach to higher spin field theories we develop a generic technique for constructing the cubic interaction vertices for N=1 supersymmetric massless higher spin fields on four, six and ten dimensional flat backgrounds. Such an approach allows formulation of the equations for cubic vertices including bosonic and fermionic higher spin fields, and the problem of finding the vertices is

We have studied the alpha-decay (AD) and spontaneous fission (SF) properties of the isotopes of Z=125, 126 and 127 superheavy nuclei. AD calculations have been performed over all the possible isotopes of Z=125-127 nuclei within the framework of Wentzel-Kramers-Brillouin (WKB) and Bohr Sommerfeld quantization condition. To broaden the perspective of the calculations, we have also utilized from the analytic

A combined PIXE and optical microscopy approach was applied to examine the dental calculus of patients with periodontal disease. PIXE was performed with the Bucharest 3 MV Tandetron with 3 MeV protons and a HPGe detector, using hydroxyapatite (HA) and other standards. Sections 30 µm thick were prepared and observed using polarization microscopy and histochemical techniques. Both methods revealed the

We studied the production of 67Cu medical radioisotope by irradiating Zn targets of natural isotopic composition by bremsstrahlung photons with endpoint energies of 30 and 40 MeV. Cross-sections per equivalent quantum of 67Cu, 64Cu, 62Zn, 63Zn, 65Zn, and 69mZn activation products were measured. The specific activities of 67Cu were found to be 2.04 and 4.78 µCi/(µA∙h∙g) at the end of the bombardment

In this study, the mathematical models suitable for natural circulation, parallel channels, and general forms of additional force under moving conditions were established. An analysis code was developed using SIMPLE algorithm. Based on the validated code, the natural circulation and parallel flow instability under typical moving conditions such as inclination, rolling, heaving, and coupled motion were

A set of interfacial drag correlations is proposed for describing two-phase flows under thermal–hydraulic conditions of a horizontal steam generator (SG). This set of correlations takes into account the peculiarities of the two-phase flow in different regions of the SG. Four characteristic regions are considered: tube bundles, tube-free zones in the SG lower part, zone between the outlet from the tube

The IAEA has proposed to apply a graded approach that takes the safety measures commensurate with the magnitude of risk in decommissioning of nuclear power plants (NPPs). In this paper, the basic concept of the safety evaluation method to support development of the decommissioning plan of NPPs by applying a graded approach was established. The severity of consequence of radiation exposure risk to the

The Sodium-Cooled Fast Reactor (SFR) system, which features a fast-spectrum, sodium-cooled reactor and a closed fuel cycle for efficient management of actinides and conversion of fertile uranium, is rather prominent in the nuclear reactor design in Generation IV (Gen IV), and likely to be widespreadly used and well-constructed all over the world. However, molten sodium may be sprayed into the ambient

The main feed water flow for nuclear power units is measured by Venturi tubes. These use the principle of differential pressure to act as throttling devices. Over the course of their operational life, the passage of medium- and high-speed fluids can erode Venturi tubes, undermining the measurement accuracy of the differential pressure and flow. Venturi tubes play a vital role in nuclear power units