Trimon: An Efficient Multigroup Monte Carlo Neutron Transport Code For Triga Reactors
In this research, TRIMON, a multigroup Monte Carlo core management code for TRIGA Mark-II reactors has been developed. Furthermore, TRIMON enables direct empirical fuel burnup consideration, where the fuel burnup effect on reactor criticality is considered independently without the need for an ex...
| Main Author: | Omar, Muhammad Rabie |
|---|---|
| Format: | Thesis |
| Language: | English |
| Published: |
2020
|
| Subjects: | |
| Online Access: | http://eprints.usm.my/55113/ http://eprints.usm.my/55113/1/2___FINAL_THESIS%20cut.pdf |
Similar Items
Improvement of neutron collimator design for thermal neutron radiography using Monte Carlo-Particle transport code version 5
by: Supramaniam, Thiagu
Published: (2007)
by: Supramaniam, Thiagu
Published: (2007)
Neutron Flux Measurements With Monte Carlo Verification At The Thermal Column Of A Triga Mark II Reactor : Feasibility Study For A BNCT Facility [QC793.5.N462 E34 2008 f rb].
by: Eid Abdel_Munem, Eid Mahmoud
Published: (2008)
by: Eid Abdel_Munem, Eid Mahmoud
Published: (2008)
Spatial resolution of neutron radiography system by Nomte Carlo simulation
by: Wan Hassan, Wan Muhamad Saridan, et al.
Published: (2007)
by: Wan Hassan, Wan Muhamad Saridan, et al.
Published: (2007)
Formulation Of A High-Fidelity Nuclear Fission Sites Convergence Detection Method In Monte Carlo Reactor Safety Assessments
by: Chin, Ken Fui
Published: (2023)
by: Chin, Ken Fui
Published: (2023)
Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali
by: Zahali, Nur Zarifah
Published: (2017)
by: Zahali, Nur Zarifah
Published: (2017)
Determination of neutron flux parameters in PUSPATI TRIGA Mark II Research Reactor, Malaysia
by: I. A., Alnour, et al.
Published: (2013)
by: I. A., Alnour, et al.
Published: (2013)
Modified reconstruction of neutron spectrum emitted in dense plasma focus devises by MCNP code and monte-carlo method.
by: Roomi, A., et al.
Published: (2011)
by: Roomi, A., et al.
Published: (2011)
Analytical band Monte Carlo simulation of electron impact ionization in In[sub 0.53]Ga[sub 0.47]As
by: Choo, K. Y., et al.
Published: (2004)
by: Choo, K. Y., et al.
Published: (2004)
Multi-layer Radiation Shielding Design For Compact Proton Therapy System Using Monte Carlo Simulation
by: Aliyah, Fitrotun
Published: (2024)
by: Aliyah, Fitrotun
Published: (2024)
Monte Carlo investigation on neutron dosimetry parameters of 252Cf Isotron brachytherapy source
by: Ahmadi, Ome Leila, et al.
Published: (2020)
by: Ahmadi, Ome Leila, et al.
Published: (2020)
Full band Monte Carlo modeling of impact ionization, avalanche multiplication, and noise in submicron GaAs p[sup +]-i-n[sup +] diodes
by: Ong, D. S., et al.
Published: (2000)
by: Ong, D. S., et al.
Published: (2000)
Multiple characterization of some glassy-alloys as photon and neutron shields: in-silico Monte Carlo investigation
by: Perişanoğl, U., et al.
Published: (2021)
by: Perişanoğl, U., et al.
Published: (2021)
Prompt y-ray activation analysis of Martian analogues at the FRM II neutron reactor and the verification of a Monte Carlo planetary radiation environment model
by: Skidmore, M., et al.
Published: (2009)
by: Skidmore, M., et al.
Published: (2009)
A Simulation on Desired Neutron Flux for The Boron Neutron Capture Therapy (BNCT) Purpose by Using Monte Carlo N-Particle (MCNPX)
by: S., Shalbi, et al.
Published: (2020)
by: S., Shalbi, et al.
Published: (2020)
Sequential Monte Carlo in sequence
by: Nur Nabihah Rusyda, Roslan, et al.
Published: (2022)
by: Nur Nabihah Rusyda, Roslan, et al.
Published: (2022)
Automated power control system for reactor TRIGA PUSPATI
by: Ghazali, Anith Khairunnisa, et al.
Published: (2016)
by: Ghazali, Anith Khairunnisa, et al.
Published: (2016)
Current impulse response of thin InP p[sup +]-i-n[sup +] diodes using full band structure Monte Carlo method
by: You, A. H., et al.
Published: (2007)
by: You, A. H., et al.
Published: (2007)
Determining the mass attenuation coefficient, effective atomic number, and electron density of raw wood and binderless particleboards of Rhizophora spp. by using Monte Carlo simulation
by: Marashdeh, Mohammad W., et al.
Published: (2015)
by: Marashdeh, Mohammad W., et al.
Published: (2015)
Monte Carlo Modelling Of High Field Electron Transport And Impact Ionisation In Semiconductors
by: Choo , Kan Yeep
Published: (2005)
by: Choo , Kan Yeep
Published: (2005)
The lattice Monte Carlo method for solving phenomenological mass and heat transport problem
by: Belova, Irini V., et al.
Published: (2007)
by: Belova, Irini V., et al.
Published: (2007)
Neutron Scaling Laws from Numerical Experiments
by: Lee, S., et al.
Published: (2008)
by: Lee, S., et al.
Published: (2008)
Neutron Yield Scaling With Inductance
in Plasma Focus
by: Karami, Fereshteh, et al.
Published: (2015)
by: Karami, Fereshteh, et al.
Published: (2015)
Numerical Experiments on PF1000 Neutron Yield
by: Saw, S. H., et al.
Published: (2014)
by: Saw, S. H., et al.
Published: (2014)
The Effect of Specific Heat Ratio on Neutron Yield
by: Saw, S. H., et al.
Published: (2014)
by: Saw, S. H., et al.
Published: (2014)
On stochastic error and computational efficiency of the Markov Chain Monte Carlo method
by: Li, J., et al.
Published: (2014)
by: Li, J., et al.
Published: (2014)
Thermoluminescence energy response of TLD-100 subjected to photon irradiation using Monte Carlo N-particle transport code version 5
by: Asni, Hazila, et al.
Published: (2011)
by: Asni, Hazila, et al.
Published: (2011)
Current and neutron scaling for megajoule plasma
focus machines
by: Lee, S.
Published: (2008)
by: Lee, S.
Published: (2008)
Parametric Optimisation of Plasma Focus Devices for Neutron Production
by: Lim, L. K., et al.
Published: (2015)
by: Lim, L. K., et al.
Published: (2015)
The applicability of analytical-band Monte Carlo for modelling high field electron transport in GaAs
by: Choo, K Y, et al.
Published: (2004)
by: Choo, K Y, et al.
Published: (2004)
Neutron yield saturation in plasma focus: A fundamental cause
by: Lee, S.
Published: (2009)
by: Lee, S.
Published: (2009)
MCNP Dose Analysis for the Iranian Plasma Focus Neutron
Source
by: Noonbede, Masome, et al.
Published: (2015)
by: Noonbede, Masome, et al.
Published: (2015)
Validation of a clinical PET scanner using Monte Carlo simulation code: MCNP5
by: Musarudin, Marianie, et al.
Published: (2013)
by: Musarudin, Marianie, et al.
Published: (2013)
Comparison of Measured Neutron Yield Versus Pressure Curves for FMPF-3, NX2 and NX3 Plasma Focus Machines Against Computed Results Using the Lee Model Code
by: Saw, S. H., et al.
Published: (2015)
by: Saw, S. H., et al.
Published: (2015)
MATLAB simulation for loss of flow (LOF) in reactor TRIGA Puspati (RTP)
by: Anuar, Mohd Azrol Syafiee, et al.
Published: (2019)
by: Anuar, Mohd Azrol Syafiee, et al.
Published: (2019)
The influence of iteration number in PSO application for research reactor TRIGA PUSPATI
by: Abdullah, Nor Arymaswati, et al.
Published: (2017)
by: Abdullah, Nor Arymaswati, et al.
Published: (2017)
Development of kinetic Monte Carlo and Bin-Monte Carlo schemes for simulation of mixtures - vapor-liquid equilibria & adsorption
by: Nguyen, V., et al.
Published: (2013)
by: Nguyen, V., et al.
Published: (2013)
Efficient importance sampling function design for sequential Monte Carlo PHD filter
by: Hong Yoon, J., et al.
Published: (2012)
by: Hong Yoon, J., et al.
Published: (2012)
Effect of the Variation of Pressure on the Dynamics and Neutron Yield of Plasma Focus Machines
by: Arwinder, Singh*, et al.
Published: (2017)
by: Arwinder, Singh*, et al.
Published: (2017)
Current-step technique to enhance plasma focus compression and neutron yield
by: Lee, S., et al.
Published: (2012)
by: Lee, S., et al.
Published: (2012)
Underinsurance in Malaysia: the application of the Monte Carlo simulation
by: Hendon Redzuan,, et al.
Published: (2016)
by: Hendon Redzuan,, et al.
Published: (2016)
Similar Items
-
Improvement of neutron collimator design for thermal neutron radiography using Monte Carlo-Particle transport code version 5
by: Supramaniam, Thiagu
Published: (2007) -
Neutron Flux Measurements With Monte Carlo Verification At The Thermal Column Of A Triga Mark II Reactor : Feasibility Study For A BNCT Facility [QC793.5.N462 E34 2008 f rb].
by: Eid Abdel_Munem, Eid Mahmoud
Published: (2008) -
Spatial resolution of neutron radiography system by Nomte Carlo simulation
by: Wan Hassan, Wan Muhamad Saridan, et al.
Published: (2007) -
Formulation Of A High-Fidelity Nuclear Fission Sites Convergence Detection Method In Monte Carlo Reactor Safety Assessments
by: Chin, Ken Fui
Published: (2023) -
Thermal neutron flux measurement at pneumatic
transfer system (pts) of reactor triga puspati (rtp)
using neutron activation analysis (naa) / Nur Zarifah Zahali
by: Zahali, Nur Zarifah
Published: (2017)