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PSI PROTEUS FDWR-II Program Summary for SG-39: Core Re-analysis & Void Coefficient Sensitivity

Explore the experimental configurations, measurement types, and data package provided for FDWR-II at the PROTEUS reactor, focusing on core re-analysis, void coefficient sensitivity, and outlook. Sensitivity coefficients, reactivity effects, and fuel details are discussed.

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PSI PROTEUS FDWR-II Program Summary for SG-39: Core Re-analysis & Void Coefficient Sensitivity

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  1. Stefan Radman, Mathieu Hursin, Gregory Perret Paul Scherrer Institut PROTEUS FDWR-II (HCLWR) program summary for SG-39; Status of Re-analysis for Core 7, 8, void coefficient PSI, 19. Dezember 2019

  2. Outline Reminder of FDWR Experiments at PROTEUS Summary of PSI experimental data contribution to SG39 Selected results • Infinitely dilute cross sections • Kinf sensitivity coefficients • Reactivity sensitivity coefficients Conclusion and outlook PSI,

  3. FDWR-II – Experimental Configurations • FDWR Phase II • From 1985 to 1990 in PROTEUS reactor • PROTEUS is a driven system whose test zone contains the FDWR lattices • UO2/PuO2 pellets with 11% PuO2 • Pu(8/9/0/1/2): 1%, 64%, 23%, 8%, 4% • Fuel diameter: 8.46mm • Fuel total height: 84 cm • 2 axial blankets: • Udep. 0.224w% 235U • 28-cm high each • Several moderation conditions • Two triangular pitches • Different moderators (water, downterm, air) Seite 3 PSI, PSI,

  4. FDWR-II – Measurement types • K∞ measurements • Using axial and radial bucklings • Using compensation methods with auto-rod and a 252Cf source • Reactivity effects • Void volume • Moderator volume • Absorber rods Seite 5 PSI, PSI, 19. Dezember 2019

  5. FDWR-II – Measurement types • Spectral index measurements (core 7) • F5/F9 ~0.91 F1/F9 ~ 1.68 • F8/F9 ~1.14e-2 C2/F9 ~ 1.12 • C8/F9 ~7.8e-2 • Typical uncertainties F5: 1.8%, F8: 1.9%, F9:1.5%, C8: 1.8% • Reaction rate radial and axial traverses Seite 6 PSI, PSI, 19. Dezember 2019

  6. Data package provided to SG39 members C/E for kinf of Core 7 and 8 • Data provided • Pincell geometry • Fuel composition • C and E values • Calculation: MCNP and pincell models • Preferred measurement: cell method b/c smaller uncertainty Sensitivity coefficients generated from pincell models • MCNP6.1.1 & JEFF-3.1.1 • Uncertainties are provided • Infinitely diluted cross sections are provided Sensitivity coefficients tables according to SG33 format PSI,

  7. Infinitely Dilute Cross Sections 20 MeV homogeneous source in infinite pure graphite medium MCNPX-2.4 & JEFF-3.1.1 library. • 106 neutrons histories • The reaction rates and flux were tallied in the 33-energy group structure The cross sections and associated relative uncertainties (1 standard deviation) for the isotopes and reactions of the WPEC Subgroup 33 U-238 Capture PSI,

  8. K-Sensitivity Coefficients comparison Monte Carlo sensitivity coefficients • MCNP and SERPENT • Iterated Fission Probability • 10 latent generations Plot done with EmericDupont scripts. SC Comparison • Good agreement (i.e. within 1 standard deviation) sensitivity over 0.01% per % per unit lethargy. • Issue related to poor statistics with elastic and inelastic cross sections. • Uncertainty of MCNP solution looks underestimated. PSI,

  9. Void reactivity Sensitivity Coefficients Sensitivity coefficients of void reactivity • Computed with EGPT • Using kinf SC C/E can be inferred from kinf results. PSI,

  10. Outlook of Re-analysis work at PSI Master student currently working on HCLWR re-analysis(~ 3-4 months) • Development of a 3D models • Enhanced S/U analysis with comparison between codes (MCNP, SERPENT, TSUNAMI) and methods (GPT) • Look at non-kinf measurements (Spectral indices, power traverse) • Formatting of results according to specifications of SG39 Feedbacks on Data Delivery • Was it used? • Is it useful in terms of data assimilation? • What should be the next responses to be looked at? PSI,

  11. PSI,

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