Zobrazeno 1 - 10
of 413
pro vyhledávání: '"Forget Benoit"'
Autor:
Barlow Jack, Forget Benoit
Publikováno v:
EPJ Web of Conferences, Vol 302, p 07017 (2024)
A methodology for the generation of covariance data in the windowed multipole formalism for resolved resonance data was developed. Using this process, covariance matrices were created for oxygen-16, uranium-235, and uranium-238, such that sampled cro
Externí odkaz:
https://doaj.org/article/38e6658df6804cf2b817a913eef2b348
Autor:
Kendrick William Reed, Forget Benoit
Publikováno v:
EPJ Web of Conferences, Vol 302, p 05008 (2024)
Metal hydride moderators are a common material choice for moderating compact reactor designs, as their high thermal limits and high density of hydrogen make them favorable for operation. One additional attribute of metal hydrides, zirconium hydride i
Externí odkaz:
https://doaj.org/article/74643a1a83144ede85f4b9c121848f44
Autor:
Kreher Miriam, Forget Benoit
Publikováno v:
EPJ Web of Conferences, Vol 302, p 07001 (2024)
Monte Carlo neutron transport is often seen as the standard for accurate neutronics simulation of nuclear reactors in steady-state. However, the time dependent equation includes time derivatives of flux and delayed neutron precursors which are diffic
Externí odkaz:
https://doaj.org/article/9441852cf7c44830844ae8e1a400f34a
Publikováno v:
EPJ Web of Conferences, Vol 302, p 07016 (2024)
The purpose of this paper is to compare a new method called Embedded Monte Carlo (EMC) to the well-known Total Monte Carlo (TMC) method for nuclear data uncertainty propagation. Indeed, the TMC methodology is based on the use of a large number of ran
Externí odkaz:
https://doaj.org/article/5d72c643216f44b9bdbe15ad841cd4ee
Publikováno v:
EPJ Web of Conferences, Vol 302, p 07015 (2024)
For decades, the probability table technique has been used to model the behavior of neutron cross sections in the unresolved resonance region with a stochastic approach. Early work from Hwang hinted at the possibility of a universal probability distr
Externí odkaz:
https://doaj.org/article/67704f7fe89948c08fa88ff29dcc92a8
Publikováno v:
EPJ Web of Conferences, Vol 302, p 11006 (2024)
Any Monte Carlo transport code can produce 2D slice plots of geometric inputs using sampling of cell or material identifiers at each pixels’ point in space; ray-traced 3D plots of simulation geometries are generally less available or require paid o
Externí odkaz:
https://doaj.org/article/923ed9fa499d4c6a91f9e7a1e55689d5
Publikováno v:
EPJ Web of Conferences, Vol 247, p 09027 (2021)
Convenient access to accurate nuclear data, particularly data describing low-energy neutrons, is crucial for trustworthy simulations of thermal nuclear systems. Obtaining the scattering kernel for thermal neutrons (i.e., neutrons with energy ~1 eV or
Externí odkaz:
https://doaj.org/article/dbe3290e82b34923a0e4a8d05de5ebb1
A new method for directly sampling the neutron resonance upscattering effect is presented. Alternatives have relied on inefficient rejection sampling techniques or large tabular storage of relative velocities. None of these approaches, which require
Externí odkaz:
http://arxiv.org/abs/2303.08196
Autor:
Okabe, Ryotaro, Xue, Shangjie, Yu, Jiankai, Liu, Tongtong, Forget, Benoit, Jegelka, Stefanie, Kohse, Gordon, Hu, Lin-wen, Li, Mingda
In recent years, radiation mapping has attracted widespread research attention and increased public concerns on environmental monitoring. In terms of both materials and their configurations, radiation detectors have been developed to locate the direc
Externí odkaz:
http://arxiv.org/abs/2302.07099
Publikováno v:
EPJ Web of Conferences, Vol 111, p 06001 (2016)
In this work we describe the development and application of computational methods for processing neutron cross section data in the unresolved resonance region (URR). These methods are integrated with a continuous-energy Monte Carlo neutron transport
Externí odkaz:
https://doaj.org/article/c9576896c2864872ad9e7d37ace50545