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Physics and safety studies of a compact ADS design loaded with nitride fuel
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
Tokyo Institute of Technology, Department of Nuclear Engineering, Sekimoto Laboratory, Tokyo, Japan.
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.ORCID iD: 0000-0002-6082-8913
2011 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 38, no 11, 2350-2355 p.Article in journal (Refereed) Published
Abstract [en]

We have performed transient analysis of a nitride fueled and heavy liquid metal cooled accelerator driven system, in which the pitch-to-diameter ratio of pin lattice was set at 1.26. Unprotected loss-of-flow, unprotected transient-over-power and protected loss-of-heat-sink transients were simulated in a geometrical model of the suggested ADS design, using safety parameters obtained with the MCNP/MCNPX code.

Place, publisher, year, edition, pages
2011. Vol. 38, no 11, 2350-2355 p.
Keyword [en]
ADS, nitride fuel, transient analysis, 15-15Ti
National Category
Subatomic Physics Engineering and Technology
Identifiers
URN: urn:nbn:se:kth:diva-31527DOI: 10.1016/j.anucene.2011.06.022ISI: 000295759300005Scopus ID: 2-s2.0-80051872847OAI: oai:DiVA.org:kth-31527DiVA: diva2:404679
Note
QC 20110318 QC 20111107Available from: 2011-03-18 Created: 2011-03-18 Last updated: 2017-12-11Bibliographically approved
In thesis
1. Transmutation of Americium in Fast Neutron Facilities
Open this publication in new window or tab >>Transmutation of Americium in Fast Neutron Facilities
2011 (English)Licentiate thesis, comprehensive summary (Other academic)
Abstract [en]

In this thesis, the feasibility to use a medium sized sodium cooled fast reactor fully loaded with MOX fuel for efficient transmutation of americium is investigated by simulating the safety performance of a BN600-type fast reactor loaded with different fractions of americium in the fuel, using the safety parameters obtained with the SERPENT Monte Carlo code.

The focus is on americium mainly due to its long-term contribution to the radiotoxicity of spent nuclear fuel and its deterioration on core's safety parameters.

Applying the SAS4A/SASSYS transient analysis code, it is demonstrated that the power rating needs to be reduced by 6% for each percent additional americium introduction into the reference MOX fuel, maintaining 100 K margin to fuel melting, which is the most limiting failure mechanism.Safety analysis of a new Accelerator Driven System design with a smaller pin pitch-to-diameter ratio comparing to the reference EFIT-400 design, aiming at improving neutron source efficiency, was also performed by simulating performance for unprotected loss of flow, unprotected transient overpower, and protected loss-of-heat-sink transients, using neutronic parameters obatined from MCNP calculations. Thanks to the introduction of the austenitic 15/15Ti stainless steel with enhanced creep rupture resistance and acceptable irradiation swelling rate, the suggested ADS design loaded with nitride fuel and cooled by lead-bismuth eutectic could survive the full set of transients, preserving a margin of 130 K to cladding rupture during the most limiting transient.

The thesis concludes that efficient transmutation of americium in a medium sized sodium cooled fast reactor loaded with MOX fuel is possible but leads to a severe power penalty. Instead, preserving transmutation rates of minor actinides up to 42 kg/TWhth, the suggested ADS design with enhanced proton source efficiency appears like a better option for americium transmutation.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Insitute of Technology, 2011. 73 p.
Series
Trita-FYS, ISSN 0280-316X ; 2011:07
Keyword
americium, transmutation, fast reactor
National Category
Subatomic Physics Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-31518 (URN)978-91-7415-890-8 (ISBN)
Presentation
2011-03-10, FA-31, Alba Nova, Stockholm, 14:30 (English)
Opponent
Supervisors
Note
QC 20110318Available from: 2011-03-18 Created: 2011-03-17 Last updated: 2012-02-23Bibliographically approved
2. Transmutation of Am in sodium fast reactors and accelerator driven systems
Open this publication in new window or tab >>Transmutation of Am in sodium fast reactors and accelerator driven systems
2012 (English)Doctoral thesis, comprehensive summary (Other academic)
Abstract [en]

In this thesis, the feasibility to use sodium cooled fast reactors loaded with MOX, metallic and nitride fuels for efficient transmutation of americium is investigated by performing transient analysis for cases with different americium contents in fuels, using safety parameters obtained with the SERPENT Monte Carlo code. It was then demonstrated that there is no solid limit for the Am introduction into oxide, metallic and nitride fuels that were loaded into sodium fast reactors. Instead, higher Am contents could be permitted if specific levels of power penalty were accepted.

Transient analysis of a new Accelerator Driven System design with higher neutron source efficiency than the reference EFIT-400 design, was also performed. Based on simulation results, the suggested ADS design was proved to survive the full set of transients, preserving 130 K margin to cladding rupture during the most limiting transient.

After comparing Am transmutation performances in SFRs and the suggested ADS, it can be concluded that: 1. Nitride fuel could provide the highest Am transmutation efficiency, when loaded into SFRs; 2. One SFR loaded with nitride fuel is sufficient to transmute Am inventory produced by more than 15 commercial LWRs within the same time period, which is three times higher than the supporting ratio reported for the suggested ADS; 3. The total fraction of ADS power in the power park is half of cases for critical reactors.

Place, publisher, year, edition, pages
Stockholm: KTH Royal Institute of Technology, 2012. xiii, 72 p.
Series
Trita-FYS, ISSN 0280-316X ; 2012:05
Keyword
Sodium cooled fast reactor, accelerator driven system, americium, transmutation, transient analysis
National Category
Other Physics Topics
Identifiers
urn:nbn:se:kth:diva-72427 (URN)978-91-7501-254-4 (ISBN)
Public defence
2012-02-14, Sal FA31, Roslagstullsbacken 21, AlbaNova, Stockholm, Sweden, 10:15 (English)
Opponent
Supervisors
Note
QC 20120201Available from: 2012-02-01 Created: 2012-01-31 Last updated: 2012-02-01Bibliographically approved

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