Neutron transport
Neutron Transport Analysis of the Processes Affecting the in situ Calibration of ITER In-Vessel Neutron Flux Monitors Equipped with a Micro-Fission Chamber System
... via neutron transport analysis using MCNP, the various effects mentioned above on the calibration time and the detection efficiency of the MFC were ...in-vessel neutron flux monitor equipped with a MFC ...
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The Study for Transient Neutron Transport with Pomrning-Eddington Approximation
... time-dependent neutron transport problem is approximated using the Pomraning-Eddington ...the neutron energy density and net flux, which can be used to calculate the neutron angular intensity ...
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hp Adaptive discontinuous Galerkin methods for neutron transport criticality problems
... of neutron transport is an active area of research that has continued to be developed over the last seventy ...nowadays, neutron transport theory is ex- ploited in applications ranging from ...
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The jN Method for Neutron Transport Problems in a Homogeneous Slab EUR 3620
... method a new analytical approach is applied within the N context of a multigroup model to solve neutron transport problems for an infinite homogeneous slab with finite thickness under th[r] ...
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Predicting Ex-core Detector Response in a PWR with Monte Carlo Neutron Transport Methods
... and neutron flux distribution inside the reactor core can be analysed and redistribution due to the control rod movement can be ...the neutron source for the MCNP ex-core ...ex-core neutron detectors ...
8
Neutron transport calculation for Activation Evaluation for Decommissioning of PET cyclotron Facility
... Abstract. In order to evaluate the state of activation in a cyclotron facility used for the radioisotope production of PET diagnostics, we measured the neutron flux by using gold foils and TLDs. Then, the spatial ...
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A Residual-Based A Posteriori Spatial Error Estimator for the SN Neutron Transport Equation.
... In neutron transport they have developed and implemented an h-adaptivity scheme utilizing a two-mesh difference-based error estimator in which a solution on a uniformly-refined mesh, integrated over angle ...
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Hybrid Deterministic/Monte Carlo Methods for Solving the Neutron Transport Equation and k-Eigenvalue Problem.
... the neutron scalar and angular flux by solving partial differential equations, namely the neutron transport equation and its angular ...the neutron transport equation can be quite ...
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Analytical solutions for the neutron transport using the spectral methods
... A variety of numerical methods for the neutron transport equation have been pro- posed in the literature. In general, these methods are based on using quadrature formu- las for the discretization of the ...
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Cosmic ray neutron transport at a forest field site: the sensitivity to various environmental conditions with focus on biomass and canopy interception
... Cosmic-ray neutron intensity is inversely corre- lated to all hydrogen present in the upper decimeters of the subsurface and the first few hectometers of the atmosphere above the ground ...cosmic-ray ...
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TIMOC A General Purpose Monte Carlo Code for Stationary and Time Dependent Neutron Transport EUR 4519
... ABSTRACT TIMOC is a Monte Carlo Code for the solution of the energy and time dependent or stationary neutron transport equation in 3-dimensional geometries.. It is written in FORTRAN II [r] ...
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Direct Discrete Method (DDM) and its Application to Neutron Transport Problems
... the Neutron Transport Equation and more compatible with the physical meanings of the ...the neutron transport dierential ...multigroup neutron transport discrete equation has ...
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The Foundations of Neutron Transport Theory
... 5.38 The first four terms in this expression are strict analogues of the corresponding scattering contributions to the balance relation for the singlet density as seen in Equation 5.1.. [r] ...
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A Posteriori Error Estimators for the Discrete Ordinates Approximation of the One-Speed Neutron Transport Equation
... Fournier, Le Tellier and Suteau in [13] have applied an estimator derived for hyperbolic problems in [1], to the Discrete Ordinate DGFEM transport equation. The estimator is constructed by considering a modified ...
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Neutron Transport in a Spherical Reactor, A Study in the Application of the jN Approximation of the Multiple Collision Method EUR 2627
... The critical radii for bare spheres, calculated by using the j N approximation in combination with a one-group model, are compared with those obtained from the S N method and the exact v[r] ...
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Simulation of neutron transport for the purpose of neutron filters optimization in the pulsed neutron logging apparatus
... That kind of neutron distribution in the models can be explained as follows. As in the case considered in the previous section, in consequence of high hydrogen content in the nylon, part of the neutrons slowdown ...
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Polynomial axial expansion in the Method of Characteristics for neutron transport in 3D extruded geometries
... Characteristics (SC) approximation is used in each of them to represent the solution of the transport problem. Since the biggest degree of heterogeneities is found along the radial direction, the idea proposed in ...
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Elementary Methods in Fast Neutron Transport Theory EUR 3457
... SYROS European Atomic Energy Community — EURATOM Joint Nuclear Research Center — Ispra Establishment Italy Reactor Physics Department — Reactor Theory and Analysis Brussels, April 1967 -[r] ...
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Development and validation of uncertainty neutron transport calculations at an industrial scale
... they are not shown in this paper. IFP method has been developed for continuous energy Monte Carlo code to calculate adjoint fl ux by counting the expected fi ssion neutrons produced in some future time after a ...
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Time dependent monoenergetic neutron transport in two adjacent semi infinite media
... Erdmann An exact solution to the monoenergetic Boltzmann equation is obtained for the case of a plane isotropic burst of neutrons introduced at the interface separating two adjacent, dis[r] ...
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