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.

Investigations of radiation shielding using Monte Carlo method and elastic properties of PbO-SiO2-B2O3-Na2O glasses

2018 ◽  
Vol 18 (6) ◽  
pp. 717-727 ◽  
Author(s):  
Shams A.M. Issa ◽  
Yasser B. Saddeek ◽  
H.O. Tekin ◽  
M.I. Sayyed ◽  
Khamies saber Shaaban
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Elastic Properties ◽  
Radiation Shielding

scholarly journals Radiation shielding parameters of some antioxidants using Monte Carlo method

2018 ◽  
Vol 44 (4) ◽  
pp. 579-590 ◽  
Author(s):  
Huseyin Ozan Tekin ◽  
Mesut Karahan ◽  
Turker Tekin Erguzel ◽  
Tugba Manici ◽  
Muhsin Konuk
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Radiation Shielding

Shielding Design and Analysis for the Proton Tube of China Lead-Alloy Cooled Research Reactor (CLEAR-I)

2013 ◽  
Author(s):  
Bin Li ◽  
Qi Yang ◽  
Jun Zou ◽  
Qin Zeng ◽  
Yunqing Bai
Keyword(s):  
Research Reactor ◽  
Working Time ◽  
Lead Alloy ◽  
Optimization Analysis ◽  
Potential Exposure ◽  
Design And Optimization ◽  
System A ◽  
Shielding Design ◽  
Subcritical System

In China Lead Alloy Cooled Research Reactor (CLEAR-I), which is an accelerator driven subcritical system, a proton tube inserts into core from the top of reactor. Some neutrons will leak out along the proton tube, inducing structure materials damage and potential exposure danger for workers. The shielding design and optimization analysis for the proton tube of CLEAR-I was conducted using the VisualBUS system developed by FDS Team in this study. The result indicated that during operation allowed working time at outside containing compartment above the reactor shall not exceed 40 hours per week and entering into containing compartment was forbidden. Above results showed that the design after optimization basically met the requirements of shielding.

Computational validation of the fission rate distribution experimental benchmark at the JSI TRIGA Mark II research reactor using the Monte Carlo method

2018 ◽  
Vol 112 ◽  
pp. 94-108 ◽  
Author(s):  
Žiga Štancar ◽  
Loïc Barbot ◽  
Christophe Destouches ◽  
Damien Fourmentel ◽  
Jean-François Villard ◽  
...  
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Research Reactor ◽  
Fission Rate ◽  
Rate Distribution ◽  
The Monte Carlo Method ◽  
Triga Mark Ii ◽  
Computational Validation

scholarly journals Introduction of “Guideline for radiation shielding evaluation of transport casks by Monte Carlo method” -the outline of guideline draft-

2014 ◽  
Vol 4 ◽  
pp. 143-146
Author(s):  
Mitsufumi Asami ◽  
Hiroaki Taniuchi ◽  
Tsutomu Matsumoto ◽  
Yukio Sakamoto ◽  
Hiroki Sakamoto
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Radiation Shielding

Analysis of Neutron Flux Measurement in Thai Research Reactor-1/Modification 1 Using the Monte Carlo Method

2014 ◽  
Vol 979 ◽  
pp. 23-26
Author(s):  
S. Sabaibang ◽  
S. Lekchaum ◽  
C. Tippayakul
Keyword(s):  
Monte Carlo ◽  
Monte Carlo Method ◽  
Neutron Flux ◽  
Measurement Technique ◽  
Flux Distribution ◽  
Research Reactor ◽  
Gold Foil ◽  
Flux Measurement ◽  
Foil Thickness ◽  
The Monte Carlo Method

This study adopts the Monte Carlo method to analyze the neutron flux measurement technique in Thai Research Reactor-1/Modification 1(TRR-1/M1) by performing simulations using MCNPX computer program. The neutron flux measurement technique being analyzed is called “gold foil activation technique”. The simulation model consists of gold foil located in the middle of in-core irradiation which is in the center of the reactor core. The variation in the calculated neutron flux is assessed by varying the gold foil thickness from approximately 500 – 800 μcm. It is found from the simulation that the calculated neutron flux can differ by 33 % when increasing the gold foil thickness by 60%. In addition, more detailed simulations to determine neutron flux distribution within the gold foil are performed to study and explain the variation in neutron flux calculated at different foil thicknesses. The simulation result shows that self-shielding effect has significant impact to the neutron flux distribution within the gold foil, and hence to the average neutron flux.

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