Zobrazeno 1 - 10
of 80
pro vyhledávání: '"V.H. Gillette"'
Publikováno v:
Nuclear Engineering and Technology, Vol 54, Iss 2, Pp 764-769 (2022)
The United Arab Emirates is currently building and operating four units of the APR-1400 developed by a South Korean vendor, Korea Electric Power Corporation (KEPCO). This paper attempts to perform APR-1400 reactor core analysis by using the well-know
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9ee1aec9d3067e04102c2b2be80c1941
http://www.sciencedirect.com/science/article/pii/S1738573321005003
http://www.sciencedirect.com/science/article/pii/S1738573321005003
Publikováno v:
Annals of Nuclear Energy. 127:68-78
The use of uranium mono-nitride (UN) fuel in light water reactors has recently received an increasing interest. Neutronic and thermal-hydraulic performance of UN and associated composite fuels have been studied lately for several types of light water
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3110b404564266365cfd367943857bc6
https://doi.org/10.1016/j.anucene.2018.11.047
https://doi.org/10.1016/j.anucene.2018.11.047
Autor:
V.H. Gillette, Andrew Petersen
Publikováno v:
Journal of Nuclear Materials. 503:157-163
A modified AIREBO potential was developed to simulate the effects of thermal annealing on the structure and physical properties of damaged graphite. AIREBO parameter modifications were made to reproduce Density Functional Theory interstitial results.
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f612b17463ac707223f219483bb8e8e8
https://doi.org/10.1016/j.jnucmat.2018.03.011
https://doi.org/10.1016/j.jnucmat.2018.03.011
Autor:
Huseyin Ozan Tekin, G. Susoy, Ozge Kilicoglu, V.H. Gillette, Mustafa Recep Kaçal, Shams A.M. Issa, Ferdi Akman, Hasan Polat
This work is part of an ongoing project to produce environmentally friendly alternative radiation shielding materials for ionizing radiation facilities such as medical and industrial areas. As a new shield, a series of Sodium Dodecatungstophosphate H
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::00d9a9c329d50a123ac9ec88a8ca2fb3
https://hdl.handle.net/20.500.12697/5472
https://hdl.handle.net/20.500.12697/5472
Autor:
Mohammad Al-Shabi, Saif Y. Alhammadi, Abdelfattah E. Eldemiery, V.H. Gillette, Abdulla A. Alktebi, Bassam A. Khuwaileh, Mamdouh El Haj Assad
Publikováno v:
Case Studies in Thermal Engineering, Vol 25, Iss, Pp 100894-(2021)
Advanced Power Reactor (APR-1400) is a Generation III+ Pressurized Water Reactor (PWRs) and has gained popularity among energy mix community. APR-1400 features enhanced safety limits to prevent a "Fukushima-type" accident scenario for a duration up t
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::68ad3fbd4452f7ddb4458b3e164df2ba
https://doi.org/10.1016/j.csite.2021.100894
https://doi.org/10.1016/j.csite.2021.100894
Autor:
Huseyin Ozan Tekin, Turker Tekin Erguzel, V.H. Gillette, Shams A.M. Issa, A.I. Elazaka, Hesham M.H. Zakaly, H. A. Saudi, A. G. Mostafa, M. Rashad
Publikováno v:
Journal of Hazardous Materials. 403:123738
In the present work, aiming to collaborate in the removal of Bypass Cement Dust (BCD) from the environment, we studied a system consisting of three glasses prepared from analytical reagent grade chemicals with the following composition: 20Na2O-20BaCl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bbab0c270427546a4f352925787fb87d
https://doi.org/10.1016/j.jhazmat.2020.123738
https://doi.org/10.1016/j.jhazmat.2020.123738
Publikováno v:
Annals of Nuclear Energy. 87:242-251
Alkaline-earth beryllium and magnesium oxides are fundamental materials in nuclear industry and thermal neutron scattering applications. The calculation of the thermal neutron scattering cross sections requires a detailed knowledge of the lattice dyn
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::6f472307a68792f79fb58779d80f1f68
https://doi.org/10.1016/j.anucene.2015.09.006
https://doi.org/10.1016/j.anucene.2015.09.006
Publikováno v:
Nuclear Instruments and Methods in Physics Research Section B: Beam Interactions with Materials and Atoms. 267:525-534
An “in situ” method to determine uranium content in mineral samples by means of detecting neutrons from 238 U spontaneous fission is presented. The method is simple, exact, reliable and passive (it does not need any external excitation source). T
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::f44811619a2c9cbcc7596f0a5492569d
https://doi.org/10.1016/j.nimb.2008.11.054
https://doi.org/10.1016/j.nimb.2008.11.054
Publikováno v:
Nuclear Technology. 160:251-256
Graphite, a key structural and moderator material in the proposed Generation IV roadmap, is expected to experience irradiation at temperatures up to 1800 K. In this study, a molecular dynamics (MD) code is developed for the purpose of performing atom
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1a86135df57fa9ad851cfdad200e4b9c
https://doi.org/10.13182/nt07-a3897
https://doi.org/10.13182/nt07-a3897
Publikováno v:
IEEE Transactions on Nuclear Science. 53:3904-3911
A thermal neutron imaging facility has been set up at the North Carolina State University PULSTAR reactor. The PULSTAR is an open pool light water moderated 1 MWth research reactor with six beam tubes. The present facility is set up on beam tube # 5
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8bf0dba4612650b41a4df02af3a34740
https://doi.org/10.1109/tns.2006.884323
https://doi.org/10.1109/tns.2006.884323