Radiation shielding design for neutron diffractometers assisted by Monte Carlo methods

2006 ◽  
Vol 385-386 ◽  
pp. 1321-1323 ◽  
Author(s):  
John C. Osborn ◽  
Tunay Ersez ◽  
George Braoudakis
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Methods ◽  
Radiation Shielding ◽  
Shielding Design

Primary Shielding Design and Analysis for CLEAR-I

2013 ◽  
Author(s):  
Qi Yang ◽  
Bin Li ◽  
Chao Chen ◽  
Minghuang Wang ◽  
Qin Zeng
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Research Reactor ◽  
Natural Circulation ◽  
Radiation Shielding ◽  
Lead Alloy ◽  
Reactor Plant ◽  
Calculation System ◽  
Shielding Design ◽  
Dual Models

The China Lead-Alloy Cooled Research Reactor (CLEAR-I) is critical/sub-critical dual-models natural circulation lead alloy cooled reactor. This study is to focus on the concern radiation shielding design and analysis for CLEAR-I. The modeling program MCAM and calculation system VisualBUS developed by FDS Team was used based on Monte Carlo method and other coupled methods. As indicated by the results, the dose rate in the reactor plant (outside the containing compartment above the reactor) was below 9 uSv/h during operation and less than 1 uSv/h during shutdown, meeting with the requirements of shielding.

scholarly journals Monte Carlo Studies for the Radiation Shielding Design of LCLS-II

2013 ◽  
Author(s):  
Shanjie Xiao ◽  
Stan X. Mao ◽  
Ludovic Nicolas ◽  
Sayed H. Rokni ◽  
Mario Santana Leitner
Keyword(s):  
Monte Carlo ◽  
Radiation Shielding ◽  
Monte Carlo Studies ◽  
Shielding Design

scholarly journals RADIATION SHIELDING AND DOSE ASSESSMENT OF THE CYCLOTRON FACILITY AT INRNE-BAS

2021 ◽  
Vol 2021 (2/2021) ◽  
pp. 61-65
Author(s):  
Anguel Demerdjiev ◽  
Dimitar Tonev ◽  
Nikolai Goutev
Keyword(s):  
Monte Carlo ◽  
Nuclear Research ◽  
Radiation Shielding ◽  
Dose Assessment ◽  
Bulgarian Academy ◽  
Radiation Fields ◽  
Site Planning ◽  
Academy Of Sciences ◽  
Shielding Design ◽  
Monte Carlo Transport

The Institute for Nuclear Research and Nuclear Energy at the Bulgarian Academy of Sciences is working on the construction of a cyclotron centre. The facility is on a design level. At this stage of the project, an important task is the radiation shielding assessment of the facility. Nowadays, the Monte Carlo transport codes have become the tool of choice for solving this type of problem. In the current paper, the transport code FLUKA is used for the calculations. It is widely applied for shielding design and analysis of accelerators and their components. The distributions of the radiation fields inside and outside the cyclotron bunker are presented in this paper. Both different irradiation scenarios and bunker configurations are considered in the conducted Monte Carlo simulations. These results will be used as a guidance in site planning.

Comparison of deterministic and Monte Carlo methods in shielding design

2005 ◽  
Vol 115 (1-4) ◽  
pp. 254-257 ◽  
Author(s):  
A. D. Oliveira ◽  
C. Oliveira
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Methods ◽  
Shielding Design

MODELING OF A TURBULENT ETHYLENE/AIR JET FLAME USING HYBRID FINITE VOLUME/MONTE CARLO METHODS

2009 ◽  
Vol 1 (1) ◽  
pp. 37-53 ◽  
Author(s):  
Ranjan S. Mehta ◽  
Anquan Wang ◽  
Michael F. Modest ◽  
Daniel C. Haworth
Keyword(s):  
Monte Carlo ◽  
Finite Volume ◽  
Monte Carlo Methods ◽  
Jet Flame ◽  
Air Jet
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