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Title: Theoretical neutron damage calculations in industrial robotic manipulators used for non-destructive imaging applications

Our paper describes how to use MCNP to evaluate the rate of material damage in a robot incurred by exposure to a neutron flux. The example used in this work is that of a robotic manipulator installed in a high intensity, fast, and collimated neutron radiography beam port at the University of Texas at Austin's TRIGA Mark II research reactor. Our effort includes taking robotic technologies and using them to automate non-destructive imaging tasks in nuclear facilities where the robotic manipulator acts as the motion control system for neutron imaging tasks. Simulated radiation tests are used to analyze the radiation damage to the robot. Once the neutron damage is calculated using MCNP, several possible shielding materials are analyzed to determine the most effective way of minimizing the neutron damage. Furthermore, neutron damage predictions provide users the means to simulate geometrical and material changes, thus saving time, money, and energy in determining the optimal setup for a robotic system installed in a radiation environment.
Authors:
ORCiD logo [1] ;  [2] ; ORCiD logo [2] ;  [2]
  1. Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Univ. of Texas, Austin, TX (United States)
  2. Univ. of Texas, Austin, TX (United States)
Publication Date:
Report Number(s):
LA-UR-16-24195
Journal ID: ISSN 0149-1970
Grant/Contract Number:
AC52-06NA25396
Type:
Accepted Manuscript
Journal Name:
Progress in Nuclear Energy
Additional Journal Information:
Journal Volume: 94; Journal Issue: C; Journal ID: ISSN 0149-1970
Publisher:
Elsevier
Research Org:
Los Alamos National Lab. (LANL), Los Alamos, NM (United States)
Sponsoring Org:
USDOE
Country of Publication:
United States
Language:
English
Subject:
73 NUCLEAR PHYSICS AND RADIATION PHYSICS; Neutron radiation damage; MCNP; Radiography; Non-destructive testing; Robotics; Research reactor
OSTI Identifier:
1337108