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BELLA: a multi-point dynamics code for simulation of fast reactors
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0002-6082-8913
(English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100Article in journal (Refereed) Submitted
Abstract [en]

In this paper, the multi-point dynamics code BELLA and its benchmarking with respect to SAS4A/SASSYS- 1 is described for a small fast reactor cooled with natural convection of lead (ELECTRA). It is shown that BELLA is capable of reproducing the magnitude of mass-flow, reactivity, power and temperature excursions during design extension conditions with an accuracy better than 10%. Hence, the BELLA code can be used for safety-informed design and stability analyses of fast reactor systems, permitting to isolate essential phenomena and trends of significance for their safety assessment. 

Keyword [en]
fast reactors, dynamics, lumped parameters
National Category
Other Physics Topics
Identifiers
URN: urn:nbn:se:kth:diva-146990OAI: oai:DiVA.org:kth-146990DiVA: diva2:727138
Note

QS 2014

Available from: 2014-06-19 Created: 2014-06-19 Last updated: 2017-12-05Bibliographically approved
In thesis
1. Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead: ELECTRA: European Lead Cooled Training Reactor
Open this publication in new window or tab >>Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead: ELECTRA: European Lead Cooled Training Reactor
2014 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

In this thesis, neutronics and some relevant transient analyses of the European Lead-Cooled Training Reactor (ELECTRA) are analyzed. ELECTRA is a low-power lead-cooled fast reactor intended for training purpose. The design concept aims for the total nominal power of 0.5 MWth to be fully removed by natural circulation of pure lead, eliminating the need for pumps. A very small compact core with (Pu0.4Zr0.6)N fuel, which relies on neutron reflector to achieve criticality, results in unique reflector dominant neutronic characters. Moreover, a very hard neutron spectrum due to the choice of the fuel and the coolant leads to nearly zero Doppler feedback, relatively small effective delayed neutron fraction as well as short prompt neutron reproduction time. Nevertheless, dynamic stability and safety performance during unprotected transient scenarios are shown to be inherently ensured by the other reactivity feedbacks including the negative coolant temperature. Furthermore, the nature of the natural circulation provides favorable conditions during the studied accident cases. 

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2014. 42 p.
Series
TRITA-FYS, ISSN 0280-316X ; 2014:29
National Category
Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-146992 (URN)978-91-7595-191-1 (ISBN)
Public defence
2014-08-18, sal FA31, AlbaNova Universitetscentrum, Roslagstullsbacken 21, Stockholm, 10:00 (English)
Opponent
Supervisors
Note

QC 20140625

Available from: 2014-06-25 Created: 2014-06-19 Last updated: 2014-06-25Bibliographically approved

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Wallenius, janne

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