Change search
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf
Transmutation of Am in sodium fast reactors and accelerator driven systems
KTH, School of Engineering Sciences (SCI), Physics, Reactor Physics.
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 [en]
Sodium cooled fast reactor, accelerator driven system, americium, transmutation, transient analysis
National Category
Other Physics Topics
Identifiers
URN: urn:nbn:se:kth:diva-72427ISBN: 978-91-7501-254-4 (print)OAI: oai:DiVA.org:kth-72427DiVA: diva2:487623
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
List of papers
1. Transmutation of americium in a medium size sodium cooled fast reactor design
Open this publication in new window or tab >>Transmutation of americium in a medium size sodium cooled fast reactor design
2010 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 37, no 5, 629-638 p.Article, review/survey (Refereed) Published
Abstract [en]

We have performed transient analysis of a medium size sodium cooled reactor loaded with different fractions of americium in the fuel. Unprotected Loss of Flow (ULOF) and Unprotected Transient over Power (UTOP) accidents were simulated in a geometrical model of BN600, using safety parameters obtained with the SERPENT Monte Carlo code. For the reference case of MOX fuel, with 1 wt.% Am concentration at BOL and EOEC, the margin to melt following a design basis condition UTOP is about 100 K for a maximum linear rating of 37 kW/m. Introducing Am, the maximum fuel temperature increases by 50 K per percent Am in the fuel. In order to maintain a margin of 100 K to fuel failure, the linear rating has to be reduced by similar to 6% for each percent Am added to the fuel. Hence, an Am concentration of 2-3 wt.% in the fuel would lead to a power penalty of 6-13%, permitting a consumption rate of 1.7-3.4 kg Am/TWh(th). (C) 2009 Elsevier Ltd. All rights reserved.

National Category
Subatomic Physics Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-27895 (URN)10.1016/j.anucene.2009.12.014 (DOI)000277540000001 ()2-s2.0-77950299511 (Scopus ID)
Note
QC 20110110Available from: 2011-01-10 Created: 2011-01-03 Last updated: 2017-12-11Bibliographically approved
2. Physics and safety studies of a compact ADS design loaded with nitride fuel
Open this publication in new window or tab >>Physics and safety studies of a compact ADS design loaded with nitride fuel
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.

Keyword
ADS, nitride fuel, transient analysis, 15-15Ti
National Category
Subatomic Physics Engineering and Technology
Identifiers
urn:nbn:se:kth:diva-31527 (URN)10.1016/j.anucene.2011.06.022 (DOI)000295759300005 ()2-s2.0-80051872847 (Scopus ID)
Note
QC 20110318 QC 20111107Available from: 2011-03-18 Created: 2011-03-18 Last updated: 2017-12-11Bibliographically approved
3. Upper limits to americium concentrationin large sized sodium-cooled fast reactors loaded with metallic fuel
Open this publication in new window or tab >>Upper limits to americium concentrationin large sized sodium-cooled fast reactors loaded with metallic fuel
(English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100Article in journal (Other academic) Submitted
National Category
Physical Sciences
Identifiers
urn:nbn:se:kth:diva-72644 (URN)
Note
QS 20120328Available from: 2012-02-01 Created: 2012-02-01 Last updated: 2017-12-08Bibliographically approved
4. Transmutation of americiumin a large sized sodium-cooled fast reactor loaded with nitride fuel
Open this publication in new window or tab >>Transmutation of americiumin a large sized sodium-cooled fast reactor loaded with nitride fuel
(English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100Article in journal (Other academic) Submitted
National Category
Physical Sciences
Identifiers
urn:nbn:se:kth:diva-72645 (URN)
Note
QS 20120328Available from: 2012-02-01 Created: 2012-02-01 Last updated: 2017-12-08Bibliographically approved
5. A source efficient ADS for minor actinides burning
Open this publication in new window or tab >>A source efficient ADS for minor actinides burning
2010 (English)In: Annals of Nuclear Energy, ISSN 0306-4549, E-ISSN 1873-2100, Vol. 37, no 4, 540-545 p.Article in journal (Refereed) Published
Abstract [en]

Taking advantage of the good neutron economy of nitride fuel, a compact accelerator-driven system (ADS) for burning of minor actinide fuels has been designed, based on the fuel assembly geometry developed for the European Facility for Industrial Transmutation (EFIT) within the EUROTRANS project. The small core size of the new design permits reduction of the size of the spallation target region, which enhances proton source efficiency by about 80% compared to the reference oxide version of EFIT. Additionally, adoption of the austenitic steel 15/15Ti as clad material allows to safely reduce the fuel pin pitch, which leads to an increase of fuel volume fraction and therefore makes the neutron energy spectrum faster, consequently increasing minor actinides fission probabilities. Our calculations show that one can dramatically increase neutron source efficiency up to 0.95 without a significant loss of neutron source intensity, i.e. having high proton source efficiency. Consequently, the accelerator current required for operation of the ADS with a fission power of 201 MWth and a burn-up of 27 GW d/t per year (365 EFPD) is reduced by 67%.

Keyword
accelerator-driven systems, transmutation, fuel, neutronics, design
National Category
Subatomic Physics
Identifiers
urn:nbn:se:kth:diva-12369 (URN)10.1016/j.anucene.2009.12.025 (DOI)000276823700012 ()2-s2.0-77649181124 (Scopus ID)
Note
QC 20110324Available from: 2010-04-12 Created: 2010-04-12 Last updated: 2012-02-01Bibliographically approved

Open Access in DiVA

Final Thesis(2541 kB)907 downloads
File information
File name FULLTEXT01.pdfFile size 2541 kBChecksum SHA-512
2b320378b88a5bbf7808da2d1d1375c107b1cbfa729ce7e007d94d980aacb7f9269c424f92f84abca636b695b88fecfaa9e92ee0ec5e4c2183a5321c584ef1ed
Type fulltextMimetype application/pdf

Search in DiVA

By author/editor
Zhang, Youpeng
By organisation
Reactor Physics
Other Physics Topics

Search outside of DiVA

GoogleGoogle Scholar
Total: 907 downloads
The number of downloads is the sum of all downloads of full texts. It may include eg previous versions that are now no longer available

isbn
urn-nbn

Altmetric score

isbn
urn-nbn
Total: 401 hits
CiteExportLink to record
Permanent link

Direct link
Cite
Citation style
  • apa
  • harvard1
  • ieee
  • modern-language-association-8th-edition
  • vancouver
  • Other style
More styles
Language
  • de-DE
  • en-GB
  • en-US
  • fi-FI
  • nn-NO
  • nn-NB
  • sv-SE
  • Other locale
More languages
Output format
  • html
  • text
  • asciidoc
  • rtf