Results 11 to 20 of about 12,472 (163)

Neutron Stars—Cooling and Transport [PDF]

open access: yesSpace Science Reviews, 2015
Observations of thermal radiation from neutron stars can potentially provide information about the states of supranuclear matter in the interiors of these stars with the aid of the theory of neutron-star thermal evolution. We review the basics of this theory for isolated neutron stars with strong magnetic fields, including most relevant thermodynamic ...
Alexander Y. Potekhin   +2 more
openaire   +5 more sources

Conservative neutron transport theory [PDF]

open access: yesJournal of Mathematical Physics, 1977
A functional analytic development of the Case full-range and half-range expansions for the neutron transport equation for a conservative medium is presented. A technique suggested by Larsen is used to overcome the difficulties presented by the noninvertibility of the transport operator K−1 on its range.
Bowden, Robert L.   +2 more
openaire   +1 more source

MULTI-PHYSICS TRANSIENT SIMULATIONS WITH TRIPOLI-4® [PDF]

open access: yesEPJ Web of Conferences, 2021
In this work, we present the first dynamic calculations performed with the Monte Carlo neutron transport code TRIPOLI-4R with thermal-hydraulics feedback.
Faucher Margaux   +2 more
doaj   +1 more source

Evaluation of PWR pressure vessel fast neutron fluence benchmarks from NUREG/CR-6115 with ares transport code [PDF]

open access: yesNuclear Technology and Radiation Protection, 2017
An accurate evaluation of PWR pressure vessel fast neutron fluence is essential to ensure pressure vessel integrity over the design lifetime. The discrete ordinates method is one of the main methods to treat such problems.
Zhang Liang   +3 more
doaj   +1 more source

Analysis of the Signal over Noise Ratio of the hodoscope determined by Monte Carlo calculation [PDF]

open access: yesEPJ Web of Conferences, 2021
The CABRI experimental pulse reactor, located at the Cadarache nuclear research center, southern France, is devoted to the study of Reactivity Initiated Accidents (RIA) for the purpose of the CABRI International Program (CIP), managed by IRSN in the ...
Di Salvo J., Mirotta S., Chevalier V.
doaj   +1 more source

Dynamic Monte Carlo transient analysis for the Organization for Economic Co-operation and Development Nuclear Energy Agency (OECD/NEA) C5G7-TD benchmark

open access: yesNuclear Engineering and Technology, 2017
With ever-advancing computer technology, the Monte Carlo (MC) neutron transport calculation is expanding its application area to nuclear reactor transient analysis.
Nadeem Shaukat, Min Ryu, Hyung Jin Shim
doaj   +1 more source

Influence of the neutron transport tube on neutron resonance densitometry

open access: yesEPJ Web of Conferences, 2017
Neutron Resonance Densitometry (NRD) is a non-destructive assay technique of nuclear materials in particle-like debris that contains various materials.
Kitatani Fumito   +5 more
doaj   +1 more source

Simulation of the burnup in cell calculation using the wimsd-5b code considering different nuclear data libraries

open access: yesBrazilian Journal of Radiation Sciences, 2021
This work proposes to implement the cell calculation considering the fuel burning using the WIMSD-5B code. The cell calculation procedure allows determining the nuclear parameters present in the multi-group neutron diffusion equation and for this purpose
Desirée Yael de Sena Tavares   +2 more
doaj   +1 more source

Verification of the Discrete Ordinates Goal-Oriented Multi-Collision Source Algorithm with Neutron Streaming Problems

open access: yesEnergies, 2022
The shielding calculation of neutron streaming problems with ducts is characterized by the strong anisotropy of angular flux, which poses a challenge for the analysis of nuclear installations.
Xinyu Wang   +3 more
doaj   +1 more source

ANALYSIS AND COMPARISON OF APOLLO3® AND TRIPOLI-4® NEUTRON NOISE SOLVERS [PDF]

open access: yesEPJ Web of Conferences, 2021
Neutron noise analysis addresses the description of small time-dependent flux fluctuations in reactor cores, induced by small global or local perturbations of the macroscopic cross sections due to density fluctuations of the coolant, to vibrations of ...
Rouchon Amélie   +2 more
doaj   +1 more source

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