The impact of uncertainty in thermal scattering on nuclear ... · Ljubljana, Slovenia, 13th May...

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THE IMPACT OF UNCERTAINTY IN THERMAL SCATTERING ON NUCLEAR REACTOR PARAMETERS Luka Snoj, Ingrid Vavtar, Andrej Trkov Working Party on International Nuclear Data Evaluation Co-operation; SG48: Advances in Thermal Scattering Law Analysis Ljubljana, Slovenia, 13th May 2020

Transcript of The impact of uncertainty in thermal scattering on nuclear ... · Ljubljana, Slovenia, 13th May...

Page 1: The impact of uncertainty in thermal scattering on nuclear ... · Ljubljana, Slovenia, 13th May 2020. Outline TRIGA JSI research reactor description Experimental data Motivation Objectives

THE IMPACT OF UNCERTAINTY INTHERMAL SCATTERING ON NUCLEAR

REACTOR PARAMETERSLuka Snoj, Ingrid Vavtar, Andrej Trkov

Working Party on International Nuclear Data Evaluation Co-operation; SG48: Advances in Thermal Scattering Law AnalysisLjubljana, Slovenia, 13th May 2020

Page 2: The impact of uncertainty in thermal scattering on nuclear ... · Ljubljana, Slovenia, 13th May 2020. Outline TRIGA JSI research reactor description Experimental data Motivation Objectives

Outline■ TRIGA JSI research reactor description■ Experimental data■ Motivation■ Objectives■ Implementation■ Summary

L. Snoj: The impact of uncertainty in thermal scattering on nuclear reactor parameters WPEC SG 48

Page 3: The impact of uncertainty in thermal scattering on nuclear ... · Ljubljana, Slovenia, 13th May 2020. Outline TRIGA JSI research reactor description Experimental data Motivation Objectives

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TRIGA Mark II Reactor Ljubljana

■ 1st criticality: 31st May, 1966■ Pmax

– 250 kW (steady state)– 1 GW (pulse)

■ Fuel– UZrH (12 wt. % U)– E= 20 %

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Isothermal and water temperature reactivitycoefficient

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Pulse experiments

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■ Fuchs-Hansen model𝑃𝑃𝑚𝑚𝑚𝑚𝑚𝑚 =

𝜌𝜌𝑝𝑝2

2𝛾𝛾Λ𝐸𝐸𝑡𝑡𝑡𝑡𝑡𝑡 =

2𝜌𝜌𝑝𝑝𝛾𝛾

𝐹𝐹𝐹𝐹𝐹𝐹𝐹𝐹 =3.525Λ𝜌𝜌𝑝𝑝

𝛾𝛾 … Fuel temperature reactivity coefficientΛ = l/k … Average neutron generation time

Reproducibility of the pulse

Presenter
Presentation Notes
Peak power proportional to the square of inserted or prompt reactivity, Total energy released proportional to prompt, FWHM to the inverse of the prompt reactivity. All the pulse experiments were statistically analysed. 10 % of uncertainty in FH model was taken into account (gray area). It should be noted that it was only done for pulses which were reproduced more
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Motivation■ Difficulties in calculational reproduction of experiments■ High importance of TSL in UZrHx■ Study criticality of ultracold systems■ Fuel for small modular reactors suitable for load follow (prompt negative

temperature reactivity coefficient)

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Objectives Generate thermal neutron scattering cross sections and corresponding

covariance data in a rigorous manner, i.e. from first principles Material of interest: UZrHx (nuclear fuel in TRIGA research reactors). The thermal neutron scattering data validation on experiments Evaluation of uncertainties in physical parameters of TRIGA reactor due to

uncertainties in thermal neutron scattering law Contribute to thermal neutron scattering cross section covariances, format

and data Publicly share all experimental data and knowledge gained within the project

L. Snoj: The impact of uncertainty in thermal scattering on nuclear reactor parameters WPEC SG 48

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Implementation■ We just started posses little knowledge on the TSL topic looking for

assistance and collaboration■ CEA –JSI project on „Advances in Thermal Scattering Law Analysis“ (L. Snoj &

G. Noguère)■ Ingrid Vavtar, PhD student, advisors: Andrej Trkov, Giles Noguère■ Collaboration with Ayman Hawari (NCSU), scientific visit of Ingrid Vavtar to

NCSU planned for summer 2020 but postponed due to COVID-19■ Collaboration with WPEC SG 48

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Additional slides

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I. Vavtar: Methodology for Determining Thermal Scattering Cross Sections for Neutrons, PhD thesis presentation13/15

atomic and molecule system

generationsystem relaxation to its ground state

atomic position perturbation

interatomic force constants

VASP / QUANTUM ESPRESSO

lattice dynamics calculations

system dispersion

relationdensity of states

PHONON / PHONOPY

scattering law

LEAPR

thermal neutron scattering data

neutron transport

physical reactor parameters

MONTE CARLO TRANSPORT

CODE

Ingrid Vavtar‘s PhD thesis work plan

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Electricity production in future

• Electricity needs will greatly increase

• Generation of carbon-free electricity:• Fluctuations in electricity

generation from solar and wind sources

• Small modular reactors can provide reliable, load-following electricity

I. Vavtar: Methodology for Determining Thermal Scattering Cross Sections for Neutrons 5/15