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PROJECTS TERMOMEC (Thermo-mechanical Behaviour of Nuclear Fuel at High Burnup) ... IAEA Technical Meeting on Fuel Behavior under Transient and LOCA Mito city, ... – PowerPoint PPT presentation

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Title: Diapositiva 1


1
CIEMAT ACTIVITIES on FRAPCON/FRAPTRAN
APPLICATIONS (2010-2012)
2
PROJECTS
  • TERMOMEC (Thermo-mechanical Behaviour of Nuclear
    Fuel at High Burnup)
  • Sponsor CSN (Spanish Nuclear Regulatory Body)
  • Codes used FRAPCON-3.4 and FRAPTRAN-1.4
  • AICAST (Analysis of Integrity of Spent Fuel in
    Dry Storage and Transport)
  • Sponsor ENRESA (Spanish Radioactive Waste
    Management Company)
  • Code used FRAPCON-3.4

3
TERMOMEC MAIN ACTIVITIES
FRAPCON-3.4 FRAPTRAN-1.4
Ramps
RIA
Uncertainties analysis
LOCA
3rd SCIP Benchmark (R2, HALDEN)
HALDEN
OECD RIA-Benchmark (CABRI, NSRR)
CIP0-1 (deterministic)
Other cases (probabilistic)
4
AICAST MAIN ACTIVITIES
FRAPCON-3.4xt
Dry storage
Creep
Hydrogen
DHC
Embrittlement (HE)
Hydride radial reorientation (HRR)
Stage I II III
Mechanism Creep DHC HE HRR
5
SPECIFIC QUESTIONS
FRAPCON-3.4
  • Gap from plotter file different from (rclad in -
    rfuel out) (values fromprint2.f)
  • Clad thickness
  • tcc in frpcon.f axially changes (clad thinning
    due to oxide)
  • tcc in print2.f does NOT change from node to
    node (top value) ? same rclad out
  • Transmitted to ccreep.f ? stress not affected
    by axial variation

FRAPTRAN-1.4 (RIA simulations)
  • Tclad out with oxide Tclad out without oxide
    (completely spalled)
  • If clad failure ? ?ztot ? ?ztherm ?zelast ?zperm

6
RELATED PAPERS
  • L.E. Herranz, I. Vallejo, G. Khvostov, J.
    Sercombe, G. Zhou Assessment of fuel rod
    performance codes under ramp scenarios
    investigated within the SCIP project, Nuclear
    Engineering and Design 241 (2011), 815-825
  • A. Hughet, I. Vallejo, L.E. Herranz, Pretest
    modeling of CABRI CIP3-1 test with
    FRAPCON-3/FRAPTRAN Codes, 2011 Water Reactor
    Fuel Performance Meeting Chengdu, China, Sept.
    11-14, 2011
  • A. Hughet, L.E. Herranz, ASSESSMENT OF STEADY
    STATE UNCERTAINTIES IMPACT ON RIA MODELING, IAEA
    Technical Meeting on Fuel Behavior under
    Transient and LOCA Mito city, Ibaraki-ken, 19-21
    October 2011
  • I. Sagrado, I. Vallejo, L.E. Herranz, Analysis
    of CIP0-1 and CIP3-1 tests with FRAPTRAN and
    SCANAIR effect of the major codes assumptions,
    Top Fuel 2012
  • L. Herranz, F. Feria Extension of the
    FRAPCON-3.3 creep model to dry storage
    conditions, Progress in Nuclear Energy, Vol 52,
    p 634-639, 2010
  • F. Feria, L. Herranz, Evaluation of creep during
    dry storage in low and high burnup fuels, IAEA
    International Conference on Management of Spent
    Fuel from Nuclear Power Reactors, Vienna, 2010
  • F. Feria, L. Herranz, Creep assessment of Zry-4
    cladded high burnup fuel under dry storage,
    Progress in Nuclear Energy, Vol 53, p 395-400,
    2011
  • F. Feria, L. Herranz, FRAPCON-3.4 extension to
    model hydrogen effects on cladding mechanical
    behavior during dry storage, Top Fuel 2012

5 technical reports
7
THANK YOU FOR YOUR ATTENTION
8
SPECIFIC QUESTIONS. FRAPTRAN-1.4
CIP3-1
Oxide from FRAPCON-3.4 (restart)
No oxide (set to 0 restart)
Oxide ? 75-100 mm
?TOx max ? 391ºC (ouput file)
  • Changes in outside clad T very small (0-17 ºC)
  • Similar behavior in other cases (CIP0-1)

9
SPECIFIC QUESTIONS. FRAPTRAN-1.4
CIP3-1
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