MCNP Calculations for the Shielding Design of a Beam Tube to Be Installed at the Portuguese Research Reactor

2001 ◽  
pp. 755-759
Author(s):  
I. F. Gonçalves ◽  
A. G. Ramalho ◽  
I. C. Gonçalves ◽  
J. Salgado
Keyword(s):  
Research Reactor ◽  
Beam Tube ◽  
Shielding Design

scholarly journals Determination of backscattered neutrons/gammas from open beam port of a research reactor

2020 ◽  
Vol 225 ◽  
pp. 04032
Author(s):  
Anže Jazbec ◽  
Bor Kos ◽  
Vladimir Radulović ◽  
Klemen Ambrožič ◽  
Luka Snoj
Keyword(s):  
Research Reactor ◽  
Gamma Dose ◽  
Computation Model ◽  
Beam Tube ◽  
Horizontal Beam ◽  
Beam Port ◽  
Jozef Stefan Institute ◽  
Stefan Institute ◽  
Triga Mark Ii

Neutron and gamma dose rate calculations were carried out around horizontal beam tube no. 5 at the Jožef Stefan Institute (JSI) TRIGA Mark II research reactor. Results were compared to the experimental measurements in order to verify the computation model. In addition, another set of calculations and measurements was carried out, where an additional shield made out of concrete and paraffin was installed. With that configuration, we were able to study neutron and gamma scattering.

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.

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.

Preparation of a Beam Tube of the Portuguese Research Reactor to be Used in BNC and Other Activites

2001 ◽  
pp. 307-311 ◽  
Author(s):  
A. Ramalho ◽  
I. F. Gonçalves ◽  
I. C. Gonçalves ◽  
J. Salgado ◽  
M. Castro ◽  
...  
Keyword(s):  
Research Reactor ◽  
Beam Tube

Conceptual implementation stages for Moroccan PGAA/NI instruments: STAGE I & II

2020 ◽  
Vol 22 (4) ◽  
pp. 403-415
Author(s):  
H. Amsil ◽  
A. Jalil ◽  
K. Embarch ◽  
H. Bounouira ◽  
A. Didi ◽  
...  
Keyword(s):  
Neutron Activation Analysis ◽  
Activation Analysis ◽  
Research Reactor ◽  
Neutron Imaging ◽  
Prompt Gamma ◽  
Second Stage ◽  
Beam Tube ◽  
Implementation Stages ◽  
Triga Mark Ii ◽  
Gamma Neutron Activation

The first installation around the tangential beam tube of the Moroccan TRIGA Mark II research reactor comprises combined instruments for Prompt Gamma Neutron Activation Analysis (PGAA) and Neutron Imaging (NI). The implementation of this project is divided over three main stages, namely the installation of the collimator and the primary beam shutter, which is a common section for introduction inside the reactor; the PGAA instruments’ installation; and finally, the installation of the PGNAA/NI combined instruments. The entire design was planned for this project, and detailed information about the first and the second stage is described in this work.

scholarly journals Biological Shielding Design of In Vitro Test Facility Boron Neutron Capture Therapy (BNCT) at Radial Piercing Beam Port of Kartini Research Reactor Using MCNPX

2016 ◽  
Vol 1 (3) ◽  
pp. 166
Author(s):  
Widarto Widarto ◽  
Buyung Edi Prabowo
Keyword(s):  
Neutron Capture ◽  
Research Reactor ◽  
Test Facility ◽  
Neutron Capture Therapy ◽  
In Vitro Test ◽  
Boron Neutron Capture ◽  
Beam Port ◽  
Vitro Test ◽  
Shielding Design

<p>This research aimed to determine material specification of radiation biological shielding design of neutron and gamma output on radial piercing beamport of Kartini Research Reactor using MCNPX code,  as safety radiation protection purpose of in vitro / in vivo irradiation test facility. Refference input data using parameters of neutron and gamma as result simmulation researcher before  as follows Ф<sub>th</sub> is 5.00 x 10<sup>8 </sup>n.cm<sup>-2</sup>s<sup>-1</sup>, Ф<sub>epi</sub> is 1.23 x 10<sup>8</sup> n.cm<sup>-2</sup>s<sup>-1</sup>, Ф<sub>fast </sub>is 1.35 x 10<sup>9</sup> n.cm<sup>-2</sup>s<sup>-1</sup>, Ḋ<sub>γ</sub> is 2.49 x 10<sup>-3</sup> Sv.s<sup>-1</sup>, Ḋ<sub>n</sub> is 3.63 x 10<sup>-1</sup> Sv.s<sup>-1</sup>. [ Dwi W.]</p>Optimation result of simulation using MCNPX to determine specification material for radiation protection safety are parafin block with thickness  75 cm for neutron shielding  and covered by material lead (Pb) with thickness 15 cm for gamma shieding. By this optimation for the both thickness materials, determination for neutron and gamma dose rate  are as follow , Ḋ<sub>n</sub> = 1,1 x Sv.s<sup>-1</sup> and with Ḋ<sub>γ </sub>= 1,1 x 10<sup>-09 </sup>Sv.s<sup>-1</sup>. Those radiation dose rate of neutron and gamma parameters are still under requirement  of safety dose standard that is 2.78 x 10<sup>-9</sup> Sv.s<sup>-1</sup> as regulation of Regulatory Body BAPETEN. [Perka BAPETEN No. 4 Tahun 2014]. It can be concluded that by the Biological Shielding Design of In Vitro Test Facility Boron Neutron Capture Therapy (BNCT)<em> </em>at Radial Piercing Beam Port of Kartini Research Reactor Using MCNPX can operated safely.

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