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Electra: European Lead-Cooled Training Reactor
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0002-6082-8913
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
2012 (English)In: Nuclear Technology, ISSN 0029-5450, E-ISSN 1943-7471, Vol. 177, no 3, 303-313 p.Article in journal (Refereed) Published
Abstract [en]

The design of a low-power fast neutron reactor cooled by liquid lead (ELECTRA) is presented. Application of (Pu,Zr)N fuel permits the design of a core with very small volume and fuel column height, resulting in highly negative coolant, fuel, and structure temperature coefficients and very low channel pressure drop. Full design power of 0.5 MW(thermal) may be completely removed by natural circulation in the primary circuit, thus eliminating the need for pumps. Analysis of flow stability and performance under unprotected transients show that the suggested design is very safe, supporting its intended use for training and educational purposes.

Place, publisher, year, edition, pages
2012. Vol. 177, no 3, 303-313 p.
Keyword [en]
lead-cooled fast reactor, natural convection, nitride fuel
National Category
Physical Sciences
Identifiers
URN: urn:nbn:se:kth:diva-92052ISI: 000300969400002Scopus ID: 2-s2.0-84859472318OAI: oai:DiVA.org:kth-92052DiVA: diva2:512169
Note
QC 20120326Available from: 2012-03-26 Created: 2012-03-26 Last updated: 2017-12-07Bibliographically approved
In thesis
1. Design studies of ELECTRA: European Lead-Cooled Training Reactor
Open this publication in new window or tab >>Design studies of ELECTRA: European Lead-Cooled Training Reactor
2012 (English)Licentiate thesis, comprehensive summary (Other academic)
Abstract [en]

A fast neutron research reactor with heavy metal coolant is of interest for Generation IV reactor system develop- ers. In this thesis, the European Lead-Cooled Training Reactor (ELECTRA), which is a low-power lead-cooled fast reactor intended for training purposes, is analyzed. The main aim of the design is that the total nominal power of 0.5 MWth is fully removed by natural circula- tion of the pure lead, eliminating the need for pumps. In order to achieve that, an uranium free inert matrix fuel is selected. Moreover, absorber elements are placed outside the core as a segment of slowly rotating drums. Neutronics and some relevant transient analysis of such a design are discussed.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. 32 p.
Series
Trita-FYS, ISSN 0280-316X ; 2012:80
National Category
Other Physics Topics
Research subject
SRA - Energy
Identifiers
urn:nbn:se:kth:diva-104650 (URN)978-91-7501-529-3 (ISBN)
Presentation
2012-11-19, Sal FA31, AlbaNova, Roslagstullsbacken 21, Stockholm, 13:00 (English)
Opponent
Supervisors
Funder
StandUp
Note

QC 20121108

Available from: 2012-11-08 Created: 2012-11-08 Last updated: 2013-04-18Bibliographically approved
2. 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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