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Published:
Aug 18, 1995Keywords:
Diffusion Equation Neutronic Calculations Subcritical Assembly Thermal Neutron Fluxes
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The copyright of a submitted article is only transferred to the publishers if and when the article is accepted for publication. All rights reserved. No part of this publication may be reproduced, stored in a retrieval system or transmitted in any form or by any means, electronic, electrostatic, mechanical, photocopying, recording or otherwise without the prior written permission of the publishers.
Main Article Content
A Computer Modelled Nuclear Design of a Subcritical Assembly Driven by Isotopic Neutron Sources
Abstract
A computer code SUNDES, which solves the one-dimensional multi-group neutron diffusion equation, was developed and used to provide a conceptual nuclear design of a facility. The device is capable of producing high thermal neutron fluxes using isotopic neutron sources in a multiplying medium. The neutronic calculations show that thermal neutron fluxes > 1 x 107n/cm2 -s could be produced making suitable for neutron activation analysis (NAA) and for reactor physics experiments. The analysis also revealed that different thermal neutron fluxes could be produced depending on the strength of a driving isotopic neutron sources.
