Published 2000 | Version v1
Book

Analysis of safety limits of the Moroccan TRIGA MARK II research reactor

  • 1. Groupe de Physique des Reacteurs, Faculte des Sciences, Rabat (Morocco)

Description

A 2 MW TRIGA MARK II research reactor has been designed by General Atomics (GA) for the National Centre for Energy and Nuclear Sciences and Techniques (CNESTEN) in Morocco. This TRIGA reactor has the particularity of being the only TRIGA reactor designed to operate at the power level of 2 MW with the use of natural convection cooling. The main objective of this study is to check the ability of the reactor to operate at its nominal power with sufficient safety margins. The analysis of the reactor core starts from the basic reactor cells calculations which were performed for all the reactor cells using the LEOPARD code. The zone averaged group constants provided by cell calculations are used to compute the multiplication factor keff of the cold and clean core using the diffusion theory code Mcrac which is a recent version of the earlier code EXTERMINATOR-2. The main objective of the core calculations is to predict the core excess reactivity in cold zero power conditions and the power peaking factors which are very important data for the thermal hydraulic analysis of the core. For the maximum power peaking factors, our results agree with the values given by the reactor designer. Concerning the core excess reactivity, our results from both XY and RZ core calculations models lead to higher values than the results given by GA (about +2000 pcm). However, we should mention that GA results correspond probably to the minimum core excess reactivity which is guaranteed. The thermal hydraulic analysis of the TRIGA core was performed using the French code FLICA developed in CEA/Saclay for transient and study state thermal hydraulic analysis of a large variety of reactor cores. The objective of this analysis is to evaluate the main safety related parameters of the core and to ensure that they are within the safety limits in any operating conditions. The parameters considered in our study are: maximum fuel temperature, minimum DNBR and maximum void fraction. The obtained results confirm the GA conclusions except for the void fraction (the calculated values are beyond the usual accepted limits). (author)

Part of:
ISRP-8. 8th international symposium on radiation physics. Abstracts

Additional details

Publishing Information

Publisher
Faculty of Nuclear Sciences and Physical Engineering
Imprint Place
Prague (Czech Republic)
ISBN
80-01-02180-7
Imprint Title
ISRP-8. 8th international symposium on radiation physics. Abstracts
Imprint Pagination
340 p.
Journal Page Range
p. 123

Conference

Title
8. international symposium on radiation physics (ISRP-8)
Dates
5-9 Jun 2000
Place
Prague (Czech Republic)

Optional Information

Notes
The abstract in the publication is identical with that reproduced below