About this paper

Appears in:
Pages: 6655-6659
Publication year: 2015
ISBN: 978-84-606-8243-1
ISSN: 2340-1117

Conference name: 7th International Conference on Education and New Learning Technologies
Dates: 6-8 July, 2015
Location: Barcelona, Spain

USE OF SIMULATION CODES IN NUCLEAR ENGINEERING TO INCREASE THE KNOWLEDGE OF RADIATION TRANSPORT THROUGH MATTER

B. Juste, T. Barrachina, R. Miró, G. Verdú

Universitat Politecnica de Valencia (SPAIN)
This article presents the experiences in using a radiation transport computer code in assisting the teaching of Radiation Technology and Radiological Protection in the Nuclear Engineering program at the Universitat Politècnica de València (Spain).

Radiation transport through matter is complex phenomenon whose physics can be described by the Boltzmann equation, involving the interactions of different subatomic particles, like photons, electrons and/or neutrons.

The use of simulation become complex for undergraduate students since fields as Radiation Protection need good knowledge of several subjects as, computing, a high level of mathematical skills in modelling and numerical methods or a good knowledge of the physical problem to be simulated.

Furthermore, the number of courses dedicate to enhance the technical curriculum through use of computer codes applied to Nuclear Engineering are limited.

We make use on the MCNP (Monte Carlo N-Particle) code, version 5, which is able to simulate the interactions of the coupled radiation field generated by photons electrons and neutrons, to explain the different variables involved in the absorption, dispersion, attenuation, pair production, etc., of radiation by matter. This code has the advantage of having a pre- and post-processing graphical tool (Vised).

We have introduced the use of Monte Carlo radiation transport codes in the master programs taught at the Chemical and Nuclear Engineering Department at the UPV. Radiological Protection and Radiation Technology computer-aided learning courses are designed to be supported with the use of simulation techniques to analyse, design and understand the behaviour of industrial of medical devices making use of ionizing radiation. These devices include radiotherapy linear accelerators, mammographic and diagnostic X-ray machines, industrial X-ray equipment, radiation detectors, etc. Then, the goal of the courses is that the students develop the capabilities necessaries to face to complex problems, using computer codes as a tool.
@InProceedings{JUSTE2015USE,
author = {Juste, B. and Barrachina, T. and Mir{\'{o}}, R. and Verd{\'{u}}, G.},
title = {USE OF SIMULATION CODES IN NUCLEAR ENGINEERING TO INCREASE THE KNOWLEDGE OF RADIATION TRANSPORT THROUGH MATTER},
series = {7th International Conference on Education and New Learning Technologies},
booktitle = {EDULEARN15 Proceedings},
isbn = {978-84-606-8243-1},
issn = {2340-1117},
publisher = {IATED},
location = {Barcelona, Spain},
month = {6-8 July, 2015},
year = {2015},
pages = {6655-6659}}
TY - CONF
AU - B. Juste AU - T. Barrachina AU - R. Miró AU - G. Verdú
TI - USE OF SIMULATION CODES IN NUCLEAR ENGINEERING TO INCREASE THE KNOWLEDGE OF RADIATION TRANSPORT THROUGH MATTER
SN - 978-84-606-8243-1/2340-1117
PY - 2015
Y1 - 6-8 July, 2015
CI - Barcelona, Spain
JO - 7th International Conference on Education and New Learning Technologies
JA - EDULEARN15 Proceedings
SP - 6655
EP - 6659
ER -
B. Juste, T. Barrachina, R. Miró, G. Verdú (2015) USE OF SIMULATION CODES IN NUCLEAR ENGINEERING TO INCREASE THE KNOWLEDGE OF RADIATION TRANSPORT THROUGH MATTER, EDULEARN15 Proceedings, pp. 6655-6659.
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