As one of advance nuclear reactor design, capability to model and analyze the pebble bed reactor is important. Availability and capability of an accurate open source and open access software for pebble bed reactor analysis is strategic. It can broaden the involvement of more student and researcher which finally may improve the research and development in this field. Current study aim to develop the pebble bed core model and perform a criticality study of HTR-10 core design. This study exploit the capability of openMC software to model a double heterogenety geometry using a TRISO Pack Model Building based on random sequential packing and closed random packing. Physical parametric surveys of the developed model show an expected results in whi...
Double heterogeneity of randomly located pebbles in the core and Coated Fuel Particles (CFPs) in the...
ABSTRACT The Idaho National Laboratory’s deterministic neutronics analysis codes and methods were ap...
PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cyli...
As one of advance nuclear reactor design, capability to model and analyze the pebble bed reactor is ...
Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention...
This report describes the evaluation of data from the initial criticality measurement of the HTR-10 ...
High temperatur reactor (HTR) attract to be studied due to it has inherent safety characteristics an...
The applicability of the Monte Carlo code MCNP4B to the neutronic modeling of pebble-bed reactors wa...
Given the role of Gas-Graphite reactors as the fourth generation reactors and their recently renewed...
This paper documents the models available in Serpent for high temperature reactor (HTR) calculations...
This paper aims at comparing some simplified models to simulate irradiation cycles of Pu fuelled peb...
The pebble bed reactor has a flexibility to utilize a wide range of different fuel cycles without s...
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2001.Includes bi...
IN THIS THESIS, WE DEVELOP A NEW ITERATIVE HOMOGENIZATION TECHNIQUE FOR PEBBLE BED REACTORS, BASED O...
ABSTRACT The HTR Module [1] is a graphite-moderated, helium cooled pebble bed High Temperature React...
Double heterogeneity of randomly located pebbles in the core and Coated Fuel Particles (CFPs) in the...
ABSTRACT The Idaho National Laboratory’s deterministic neutronics analysis codes and methods were ap...
PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cyli...
As one of advance nuclear reactor design, capability to model and analyze the pebble bed reactor is ...
Gas-cooled nuclear reactor is a Generation IV reactor which has been receiving significant attention...
This report describes the evaluation of data from the initial criticality measurement of the HTR-10 ...
High temperatur reactor (HTR) attract to be studied due to it has inherent safety characteristics an...
The applicability of the Monte Carlo code MCNP4B to the neutronic modeling of pebble-bed reactors wa...
Given the role of Gas-Graphite reactors as the fourth generation reactors and their recently renewed...
This paper documents the models available in Serpent for high temperature reactor (HTR) calculations...
This paper aims at comparing some simplified models to simulate irradiation cycles of Pu fuelled peb...
The pebble bed reactor has a flexibility to utilize a wide range of different fuel cycles without s...
Thesis (S.B.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2001.Includes bi...
IN THIS THESIS, WE DEVELOP A NEW ITERATIVE HOMOGENIZATION TECHNIQUE FOR PEBBLE BED REACTORS, BASED O...
ABSTRACT The HTR Module [1] is a graphite-moderated, helium cooled pebble bed High Temperature React...
Double heterogeneity of randomly located pebbles in the core and Coated Fuel Particles (CFPs) in the...
ABSTRACT The Idaho National Laboratory’s deterministic neutronics analysis codes and methods were ap...
PROTEUS is a zero-power research reactor based on a cylindrical graphite annulus with a central cyli...