Zobrazeno 1 - 10
of 55
pro vyhledávání: '"Ali Pazirandeh"'
Publikováno v:
مجله علوم و فنون هستهای, Vol 35, Iss 3, Pp 40-45 (2014)
The electron energy distribution function in fuel rod gap of Busheher’s VVER-1000 nuclear reactor was investigated using the Fokker-Planck equation. In this regard, the Fokker-Planck equation was solved by using the Runge-Kutta numerical method, an
Externí odkaz:
https://doaj.org/article/c5be13b64e7e4e7188c2ec2e25720e64
Autor:
Ali Pazirandeh, Elham Shekarian
Publikováno v:
Iranian Journal of Physics Research, Vol 6, Iss 2, Pp 55-65 (2006)
In last two decades the optimal neutron energy for the treatment of deep seated tumors in boron neutron capture therapy in view of neutron physics and chemical compounds of boron carrier has been under thorough study. Although neutron absorption cros
Externí odkaz:
https://doaj.org/article/77b096346e5c4bbd8de368788a2ecae8
Autor:
Ali Pazirandeh, Mehrnaz Sadat Shariati
Publikováno v:
International Journal of Physics Research and Applications. 4:033-038
Plasma stability is the biggest challenge facing the nuclear fusion industry. One of the best methods of stability study is magnetohydrodynamic (MHD) equations, which has two linear and nonlinear states. Usually linear stability analysis is used to d
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::e062f32558b1c6a0c9b705d3752a9268
https://doi.org/10.29328/journal.ijpra.1001039
https://doi.org/10.29328/journal.ijpra.1001039
Autor:
Ali Pazirandeh
Publikováno v:
Biomedical Journal of Scientific & Technical Research. 42
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::84a493fbf883036e2420c8c24bd45aab
https://doi.org/10.26717/bjstr.2022.42.006795
https://doi.org/10.26717/bjstr.2022.42.006795
Publikováno v:
Nuclear Technology and Radiation Protection, Vol 35, Iss 3, Pp 189-200 (2020)
In this work, the average current nodal expansion method was developed for the time-dependent neutronic simulation of transients in a nuclear reactor's core. For this purpose, an adopted iterative algorithm was proposed for solving the 3-D time-depen
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::d0689fcd52ab537bc851179e0ffb3645
http://www.doiserbia.nb.rs/img/doi/1451-3994/2020/1451-39942003189V.pdf
http://www.doiserbia.nb.rs/img/doi/1451-3994/2020/1451-39942003189V.pdf
Publikováno v:
The Journal of Supercritical Fluids. 140:41-52
In this study the thermal-hydraulic analysis of the SCWR reactor with a new geometric design is discussed. In the new design, coolant and moderator circuits are separated and nanofluid has been used as coolant of the reactor core. In the performed su
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::b404f8fa1c2225e00d6d9721c7581a8f
https://doi.org/10.1016/j.supflu.2018.05.029
https://doi.org/10.1016/j.supflu.2018.05.029
Publikováno v:
Annals of Nuclear Energy. 163:108534
Mitigating of molten corium in severe accidents is a vital concern in safety of Nuclear Power. Plants (NPPs). As one of the main features, core catcher is provisioned in the design of NPPs. In order to appropriately design an ex-vessel core catcher,
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::cecef3c3b35753ca3859a820f1f1797b
https://doi.org/10.1016/j.anucene.2021.108534
https://doi.org/10.1016/j.anucene.2021.108534
Autor:
Ali Pazirandeh, A. Hooshyar Mobaraki
Publikováno v:
Kerntechnik. 82:303-307
The safe operation of a reactor is based on feedback models. In this paper we attempted to discuss the influence of a non-uniform radial temperature distribution on the fuel rod temperature coefficient of reactivity. The paper demonstrates that the n
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ce23ba02941a78195c85f0206dedef2a
https://doi.org/10.3139/124.110662
https://doi.org/10.3139/124.110662
Publikováno v:
Iranian Journal of Physics Research, Vol 16, Iss 4, Pp 335-343 (2017)
The heat transfer process from pellet to coolant is one of the important issues in nuclear reactor. In this regard, the fuel to clad gap and its physical and chemical properties are effective factors on heat transfer in nuclear fuel rod discussion. S
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::8e40275d5bc14806cca989b37e2251f7
http://ijpr.iut.ac.ir/browse.php?a_code=A-10-1-800&slc_lang=en&sid=1
http://ijpr.iut.ac.ir/browse.php?a_code=A-10-1-800&slc_lang=en&sid=1
Publikováno v:
Reports of Practical Oncology & Radiotherapy. 22:42-51
Aim A new model of liver phantom is defined, then this model is simulated by MCNPX code for dosimetry in neutron radiation therapy. Additionally, an analytical method is applied based on neutrons collisions and mathematical equations to estimate abso
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_dedup___::10cf1fc0a90d41ee944aee2637bc2724
https://doi.org/10.1016/j.rpor.2016.09.013
https://doi.org/10.1016/j.rpor.2016.09.013