| 1. |
- Bortot, Sara, 1983-, et al.
(författare)
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BELLA : a multi-point dynamics code for simulation of fast reactors
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Ingår i: Annals of Nuclear Energy. - 0306-4549 .- 1873-2100.
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Tidskriftsartikel (refereegranskat)abstract
- 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.
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| 2. |
- Suvdantsetseg, Erdenechimeg, 1983-, et al.
(författare)
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Optimization of the reactivity control drum system of ELECTRA
- 2012
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Ingår i: Nuclear Engineering and Design. - : Elsevier. - 0029-5493 .- 1872-759X. ; 252:1, s. 209-214
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Tidskriftsartikel (refereegranskat)abstract
- In this paper, an optimized control drum system for the European Lead Cooled Training Reactor (ELECTRA) is proposed. By changing the number of rotating drums from 6 to 12, we succeed in reducing the maximum rotational worth of a single drum from 4 $ to 1.64 $. As a consequence, the safety margin during reactivity insertions is significantly improved.
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| 3. |
- Suvdantsetseg, Erdenechimeg, 1983-, et al.
(författare)
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An assessment of prompt neutron reproduction time in a reflector dominated fast critical system : ELECTRA
- 2014
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Ingår i: Annals of Nuclear Energy. - : Elsevier BV. - 0306-4549 .- 1873-2100. ; 71, s. 159-165
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Tidskriftsartikel (refereegranskat)abstract
- In this paper, an accurate method to evaluate the prompt neutron reproduction time for a reflector dominated fast critical reactor, ELECTRA, is discussed. To adequately handle the problem, explicit time dependent Monte Carlo calculations with MCNP, applying repeated time cut-off technique, is used and compared against the σ ∼ 1/v time dependent absorber method, applying artificial cross section data in the Monte Carlo code SERPENT. The results show that when a reflector plays a major role in criticality for fast neutron reactor, the two methods predict different physical parameters (Λ = 69 ± 2 ns and Λ = 83 ± 1 ns for time cut-off and the 1/v method respectively). The reason is explained by applying Avery-Cohn’s two-region prompt neutron model.
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| 4. |
- Suvdantsetseg, Erdenechimeg, 1983-
(författare)
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Design studies of ELECTRA : European Lead-Cooled Training Reactor
- 2012
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Licentiatavhandling (övrigt vetenskapligt/konstnärligt)abstract
- 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.
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| 5. |
- Suvdantsetseg, Erdenechimeg, 1983-
(författare)
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Neutronics and Transient Analysis of a Small Fast Reactor Cooled with Natural Circulation of Lead : ELECTRA: European Lead Cooled Training Reactor
- 2014
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Doktorsavhandling (övrigt vetenskapligt/konstnärligt)abstract
- 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.
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| 6. |
- Suvdantsetseg, Erdenechimeg, 1983-, et al.
(författare)
-
Unprotected Loss of Heat Sink Analysis for the Design of ELECTRA
-
Ingår i: Annals of Nuclear Energy. - 0306-4549 .- 1873-2100.
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Tidskriftsartikel (övrigt vetenskapligt/konstnärligt)abstract
- In this paper, the transient behavior of a small fast reactor cooled by natural convection of lead (ELECTRA) is studied under unprotected loss of heat sink conditions, as a parametric function of the radiative heat loss via its outer vessel surface. The results show that when this heat loss is higher than the decay heat level, the negative reactivity feedback mechanisms of the system lead to re-criticality, bringing it into a new steady state. As a consequence, coolant freezing may be avoided during such accidents.
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