Results 21 to 30 of about 16,330 (259)
Characterization of the light and flexible nonlead aprons as an alternative to Pb-PVC. [PDF]
J Appl Clin Med PhysAbstract Background Radiation shielding is crucial for protecting healthcare professionals from scatter radiation during x‐ray procedures. Conventional lead aprons, although effective, are limited by their high weight, low flexibility, and potential toxicity.
Khorami MT, Salehi Z.
europepmc +2 more sources
Recent MCNP developments [PDF]
IEEE Transactions on Nuclear Science, 1992 The authors report both the status and developments in the Monte Carlo neutron-photon (MCNP) radiation transport computer code and two items of more general interest to computational physics: the accuracy of modern physics computer codes and the performance of scientific workstations.
Hendricks, J.S., Briesmeister, J.F.
openaire +2 more sources
MCNP: Photon benchmark problems [PDF]
, 1991 The recent widespread, markedly increased use of radiation transport codes has produced greater user and institutional demand for assurance that such codes give correct results. Responding to these pressing requirements for code validation, the general purpose Monte Carlo transport code MCNP has been tested on six different photon problem families ...
Whalen, Daniel J. +2 more
openaire +3 more sources
MCNP variance reduction overview [PDF]
, 2006 The MCNP code is rich in variance reduction features. Standard variance reduction methods found in most Monte Carlo codes are available as well as a number of methods unique to MCNP. We discuss the variance reduction features presently in MCNP as well as new ones under study for possible inclusion in future versions of the code.
Hendricks, J. S., Booth, T. E.
openaire +2 more sources
SCIENTIFIC WORKFLOWS FOR MCNP6 AND PROTEUS WITHIN THE NEAMS WORKBENCH [PDF]
EPJ Web of Conferences, 2021 In this work we integrate MCNP and PROTEUS, two high-fidelity reactor physics codes, into the Nuclear Energy Advanced Modeling and Simulation (NEAMS)Workbench.
Dominesey Kurt A. +3 more
doaj +1 more source
BENCHMARKING OF THE SERPENT 2 MONTE CARLO CODE FOR FUSION NEUTRONICS APPLICATIONS [PDF]
EPJ Web of Conferences, 2021 Analyses of radiation fields resulting from a deuterium-tritium (DT) plasma in fusion devices is a critical input to the design and validation of many aspects of the reactor design, including, shielding, material lifetime and remote maintenance ...
Valentine A. +3 more
doaj +1 more source
Analysis of the Signal over Noise Ratio of the hodoscope determined by Monte Carlo calculation [PDF]
EPJ 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
Assessment of the gamma and neutron dose field around the closed-water activation loop at the JSI TRIGA reactor [PDF]
EPJ Web of Conferences, 2023 A closed-water activation loop is being built at the Jožef Stefan Institute TRIGA reactor in Slovenia to serve as a well-defined and stable source of high-energy gamma rays and neutrons.
Kotnik Domen, Snoj Luka, Lengar Igor
doaj +1 more source
Industria: Jurnal Teknologi dan Manajemen Agroindustri, 2021 Activated charcoal and imarsil (local adsorbent) had shown significant Aflatoxin (AF) decontamination potentials in vegetable oil at a low AF contamination level of ≤ 9 ng/L.
Oluyinka Eunice Aringbangba +4 more
doaj +1 more source
Graphical Visualisation of the MCNP Mesh Tally File
Journal of Energy - Energija, 2023 This paper presents an updated version of the MTV3D (Mesh Tally Visualization in 3D) program with Windows graphical user interface for visualization of the MCNP-based mesh tally files. Several improvements over the previous program version are addressing
M. Matijević +2 more
semanticscholar +1 more source