TMS On-the-fly Temperature Treatment in Serpent

Similar documents
Temperature treatment capabilites in Serpent 2(.1.24)

On-the-fly Doppler Broadening in Serpent

Serpent Monte Carlo Neutron Transport Code

Demonstration of Full PWR Core Coupled Monte Carlo Neutron Transport and Thermal-Hydraulic Simulations Using Serpent 2/ SUBCHANFLOW

In the Memory of John Rowlands

On-The-Fly Neutron Doppler Broadening for MCNP"

Monte Carlo neutron transport and thermal-hydraulic simulations using Serpent 2/SUBCHANFLOW

Neutronic analysis of SFR lattices: Serpent vs. HELIOS-2

Dissertation. Development of a stochastic temperature treatment technique for Monte Carlo neutron tracking. Tuomas Viitanen

Full-core Reactor Analysis using Monte Carlo: Challenges and Progress

On-the-Fly Sampling of Temperature-Dependent Thermal Neutron Scattering Data for Monte Carlo Simulations

CASMO-5/5M Code and Library Status. J. Rhodes, K. Smith, D. Lee, Z. Xu, & N. Gheorghiu Arizona 2008

FULL CORE POWER AND ISOTOPIC OSCILLATIONS WITH VARIOUS DEPLETION SCHEMES

Uncertainty quantification using SCALE 6.2 package and GPT techniques implemented in Serpent 2

Preventing xenon oscillations in Monte Carlo burnup calculations by forcing equilibrium

Energy Dependence of Neutron Flux

Study of Predictor-corrector methods. for Monte Carlo Burnup Codes. Dan Kotlyar Dr. Eugene Shwageraus. Supervisor

USE OF LATTICE CODE DRAGON IN REACTOR CALUCLATIONS

Extension of the MCBEND Monte Carlo Code to Perform Adjoint Calculations using Point Energy Data

Cross Section Generation Strategy for High Conversion Light Water Reactors Bryan Herman and Eugene Shwageraus

SG39 Meeting May 16-17, Update on Continuous Energy Cross Section Adjustment. UC Berkeley / INL collaboration

Elastic scattering. Elastic scattering

Development of Multigroup Cross Section Generation Code MC 2-3 for Fast Reactor Analysis

Figure 1. Layout of fuel assemblies, taken from BEAVRS full core benchmark, to demonstrate the modeling capabilities of OpenMC.

Upcoming features in Serpent photon transport mode

Implementation of new adjoint-based methods for sensitivity analysis and uncertainty quantication in Serpent

Click to edit Master title style

Reconstruction of Neutron Cross-sections and Sampling

Vladimir Sobes 2, Luiz Leal 3, Andrej Trkov 4 and Matt Falk 5

BURNUP CALCULATION CAPABILITY IN THE PSG2 / SERPENT MONTE CARLO REACTOR PHYSICS CODE

COMPARATIVE ANALYSIS OF WWER-440 REACTOR CORE WITH PARCS/HELIOS AND PARCS/SERPENT CODES

CALCULATION OF TEMPERATURE REACTIVITY COEFFICIENTS IN KRITZ-2 CRITICAL EXPERIMENTS USING WIMS ABSTRACT

Lecture 3 Nuclear Data Neutron Interactions and Applications Spring 2010

New Approaches and Applications for Monte Carlo Perturbation Theory.

Sodium void coefficient map by Serpent

Higher-order Chebyshev Rational Approximation Method (CRAM) and application to Burnup Calculations

RANDOMLY DISPERSED PARTICLE FUEL MODEL IN THE PSG MONTE CARLO NEUTRON TRANSPORT CODE

KEYWORDS: chord length sampling, random media, radiation transport, Monte Carlo method, chord length probability distribution function.

On the Chord Length Sampling in 1-D Binary Stochastic Media

CROSS SECTION WEIGHTING SPECTRUM FOR FAST REACTOR ANALYSIS

Convergence Analysis and Criterion for Data Assimilation with Sensitivities from Monte Carlo Neutron Transport Codes

MONTE CARLO SIMULATION OF VHTR PARTICLE FUEL WITH CHORD LENGTH SAMPLING

Complete activation data libraries for all incident particles, all energies and including covariance data

THE NEXT GENERATION WIMS LATTICE CODE : WIMS9

Reactors and Fuels. Allen G. Croff Oak Ridge National Laboratory (ret.) NNSA/DOE Nevada Support Facility 232 Energy Way Las Vegas, NV

Resonance self-shielding methodology of new neutron transport code STREAM

Overview of SCALE 6.2

FRENDY: A new nuclear data processing system being developed at JAEA

Sensitivity and Uncertainty Analysis Methodologies for Fast Reactor Physics and Design at JAEA

Perturbation/sensitivity calculations with Serpent

A PERTURBATION ANALYSIS SCHEME IN WIMS USING TRANSPORT THEORY FLUX SOLUTIONS

Vectorization of Continuous Energy Monte Carlo Method for Neutron Transport Calculation

QUADRATIC DEPLETION MODEL FOR GADOLINIUM ISOTOPES IN CASMO-5

Chapter 2 Nuclear Reactor Calculations

A.BIDAUD, I. KODELI, V.MASTRANGELO, E.SARTORI

Testing of the SERPENT 2 Software Package and Calculation of the VVR-ts Research Reactor Lifetime

A PWR ASSEMBLY COMPUTATIONAL SCHEME BASED ON THE DRAGON V4 LATTICE CODE

Use of Monte Carlo and Deterministic Codes for Calculation of Plutonium Radial Distribution in a Fuel Cell

Challenges in Prismatic HTR Reactor Physics

Nuclear Data Uncertainty Analysis in Criticality Safety. Oliver Buss, Axel Hoefer, Jens-Christian Neuber AREVA NP GmbH, PEPA-G (Offenbach, Germany)

Reactor Physics: Basic Definitions and Perspectives. Table of Contents

A TEMPERATURE DEPENDENT ENDF/B-VI.8 ACE LIBRARY FOR UO2, THO2, ZIRC4, SS AISI-348, H2O, B4C AND AG-IN-CD

Lesson 14: Reactivity Variations and Control

Neutron Interactions with Matter

Treatment of Implicit Effects with XSUSA.

Comparison of the Monte Carlo Adjoint-Weighted and Differential Operator Perturbation Methods

On the use of SERPENT code for few-group XS generation for Sodium Fast Reactors

Technical workshop : Dynamic nuclear fuel cycle

Cost-accuracy analysis of a variational nodal 2D/1D approach to pin resolved neutron transport

Sensitivity and Uncertainty Analysis of the k eff and b eff for the ICSBEP and IRPhE Benchmarks

MCNP6: Fission Multiplicity Model Usage in Criticality Calculations

Nuclear Fission. 1/v Fast neutrons. U thermal cross sections σ fission 584 b. σ scattering 9 b. σ radiative capture 97 b.

Covariance Generation using CONRAD and SAMMY Computer Codes

Parametric Studies of the Effect of MOx Environment and Control Rods for PWR-UOx Burnup Credit Implementation

New photon transport model in Serpent 2

NEUTRON PHYSICAL ANALYSIS OF SIX ENERGETIC FAST REACTORS

Error Estimation for ADS Nuclear Properties by using Nuclear Data Covariances

Reactivity Coefficients

Low-Energy Neutron Treatment in FLUKA. Beginners FLUKA Course

New Capabilities for the Chebyshev Rational Approximation method (CRAM)

Simulating Gamma-Ray Telescopes in Space Radiation Environments with Geant4: Detector Activation

Lewis 2.1, 2.2 and 2.3

Chapter V: Interactions of neutrons with matter

Criticality analysis of ALLEGRO Fuel Assemblies Configurations

3.12 Development of Burn-up Calculation System for Fusion-Fission Hybrid Reactor

Research Article Calculations for a BWR Lattice with Adjacent Gadolinium Pins Using the Monte Carlo Cell Code Serpent v.1.1.7

ARTICLE. EASY-II(12): a system for modelling of n, d, p, γ, α activation and transmutation processes

Spatially Dependent Self-Shielding Method with Temperature Distribution for the Two-Dimensional

EVENT-BY-EVENT MONTE CARLO TRACKING OF NEUTRON-NUCLEUS COLLISIONS IN NEUTRON DETECTORS

NEUTRON MODERATION. LIST three desirable characteristics of a moderator.

in Cross-Section Data

Whole Core Pin-by-Pin Coupled Neutronic-Thermal-hydraulic Steady state and Transient Calculations using COBAYA3 code

BENCHMARK CALCULATIONS FOR URANIUM 235

ANALYSIS OF THE COOLANT DENSITY REACTIVITY COEFFICIENT IN LFRs AND SFRs VIA MONTE CARLO PERTURBATION/SENSITIVITY

MOx Benchmark Calculations by Deterministic and Monte Carlo Codes

A Cumulative migration method for computing rigorous transport cross sections and diffusion coefficients for LWR lattices with Monte Carlo

MC21 / CTF and VERA Multiphysics Solutions to VERA Core Physics Benchmark Progression Problems 6 and 7

DETERMINATION OF THE EQUILIBRIUM COMPOSITION OF CORES WITH CONTINUOUS FUEL FEED AND REMOVAL USING MOCUP

Benchmark Test of JENDL High Energy File with MCNP

MONTE CARLO NEUTRON TRANSPORT SIMULATING NUCLEAR REACTIONS ONE NEUTRON AT A TIME Tony Scudiero NVIDIA

Transcription:

TMS On-the-fly Temperature Treatment in Serpent Tuomas Viitanen & Jaakko Leppänen Serpent User Group Meeting, Cambridge, UK September 17 19, 2014

Effects of thermal motion on neutron transport On reaction probabilities: - Doppler-broadening of resolved and unresolved resonances - Increase in potential scattering at low energies. - Special case: bound atoms with S(α,β) tables. On collision dynamics: - Secondary particle distributions of elastic scattering. - Secondary particle distributions of bound-atom scattering. Traditionally, - Red effects are pre-calculated and - Blue effects are taken into account during the transport calculation.

On-the-fly temperature treatment Background With pre-calculated data - Cross sections need to be prepared beforehand at each temperature appearing in the system. - XS data needs to be stored at each temperature in the node memory. Memory consumption in burnup problems is between 1 30 GB per temperature appearing in the system, depending on the optimization mode and the accuracy of the library. Covering the 500 1200 K temperature range of a PWR in HFP conditions requires numerous temperatures. Problem! Solution: On-the-fly temperature treatment.

Target Motion Sampling (TMS) technique Basic idea: There are no effective cross sections, just 0 K cross sections and thermal motion of target nuclei The effect of thermal motion can be taken into account by sampling velocities at collision points and using 0 K cross sections in target-at-rest frame. To make this possible, a rejection sampling scheme (next slide) based on a temperature majorant Σ maj (E) cross section must be used in the neutron tracking. The same idea has been used for many years in PRIZMA Monte Carlo code [1]. [1] V.N. OGIBIN, A.I. ORLOV, Majorized Cross-section Method for Tracking Neutrons in Moving Media, J. Nuclear Science and Technology, Methods and Codes for Mathematical Physics Series, 2(16), pp.6 9 (1984).

TMS Temperature Treatment Method Tracking scheme 1. Sample path length l based on a majorant cross section Σ maj (E) New collision point candidate x i+1 = x i +lω 2. Sample target nuclide n: P n = Σ maj,n(e) Σ maj (E) 3. Sample target velocity from distribution ) f n (V t,µ) = v 2v f MB (T(x i+1 ) T base,a n,v t, where v is the relative (target-at-rest) velocity Target-at-rest energy E = Σ maj,n(e) n Σ maj,n(e). 4. Rejection sampling with criterion ξ < g n(e,t(x i+1 ) T base )Σ tot,n (E,T base ). Σ maj,n (E) If sample is rejected, return to 1. If sample is accepted, sample reactions in target-at-rest frame (E ). Continue accordingly.

Previous publications in short (1/3) Introduction to the TMS method (Explicit Treatment of Thermal Motion) in an NSE article [2]. - The basic idea is introduced. - Just proof-of-concept, no practical calculations. First practical results in PHYSOR2012 [3]. - A very early implementation based on a multigroup majorant results obsolete. [2] T. Viitanen and J. Leppänen, Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines, Nucl. Sci. Eng., 171, 165-173 (2012). [3] T. Viitanen and J. Leppänen, Explicit temperature treatment in Monte Carlo neutron tracking routines First results. In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, (2012).

Previous publications in short (2/3) Optimization of TMS by increasing the sampling efficiency discussed in articles [4, 5, 6] 1. Changing to a continuous-energy majorant cross section. 2. Elevating the temperature of basis cross sections above 0 K. 3. Reducing the conservativity of the majorant. - (This affects also the efficiency of DBRC!) [4] T. Viitanen and J. Leppänen, Optimizing the implementation of the target motion sampling temperature treatment technique How fast can it get?, In proc. M&C 2013, Sun Valley, ID, May 5-9, (2013). [5] T. Viitanen and J. Leppänen, Target motion sampling temperature treatment technique with elevated basis cross section temperatures., Nucl. Sci. Eng., 177, 77-89 (2014). [6] T. Viitanen and J. Leppänen, Temperature majorant cross sections in Monte Carlo neutron neutron tracking, Nucl. Sci. Eng., Accepted for publication on Aug 31. 2014.

2.5 x 104 2.5 x 104 2 2 Cross Section (b) 1.5 1 Cross Section (b) 1.5 1 0.5 0.5 0 6 6.5 7 7.5 Energy (MeV) x 10 6 0 6 6.5 7 7.5 Energy (MeV) x 10 6 Figure 1: Changing from a multi-group (left) to a continuous-energy (right) removes unnecessary conservativity by making the shape of the majorant xs conform better to the total cross section.

2.5 x 104 2 Cross Section (b) 1.5 1 0.5 0 6 6.5 7 7.5 Energy (MeV) x 10 6 2.5 x 104 2.5 x 104 2 2 Cross Section (b) 1.5 1 Cross Section (b) 1.5 1 0.5 0.5 0 6 6.5 7 7.5 Energy (MeV) x 10 6 0 6 6.5 7 7.5 Energy (MeV) x 10 6 Figure 2: It is also possible to reduce the difference between the majorant and total xs by increasing the basis temperature of the total cross section (left) and by fine-tuning the cut-off conditions in the majorant generation (right).

Previous publications in short (3/3) Effects of TMS on reaction rate estimators were studied in [7] - TMS has no practical effect on the variances of estimators. - Exception: the variances are increased near very strong resonances. Standard Deviation of Capture Rate (1/s) 12 x 109 10 8 6 4 2 0 TMS/0 K N=1 N=2 N=10 N=100 reference 5.5 6 6.5 7 7.5 8 Energy (MeV) x 10 6 [7] T. Viitanen and J. Leppänen, Effect of the Target Motion Sampling Temperature Treatment Method on the Statistics and Performance, Ann. Nucl. Energy, accepted, in-press.

Performance of TMS in Serpent 2.1.17

PWR-Gd PWR-BU Number of neutron histories 10 9 5 10 8 Reference k eff 1.15523 0.93453 k eff (pcm) 2 2 Transport time (h) 5.2 2.7 Memory requirement (GB) 3.4 91.2 FOM, Total Capture Rate ( 1 ) s 4.1E+04 5.4E+04 FOM, Capture Rate Around 6.7 ev ( 1 ) s 9.2E+02 8.7E+02 TMS k TMS k NJOY (pcm) 3 ± 3 1 ± 3 Abs. / Rel. Transport time (h/-) 6.4 / 1.24 33.2 / 12.33 Abs. / Rel. Memory requirement (GB/-) 2.5 / 0.72 34.0 / 0.37 TMS Sampling efficiency (%) 53.2 52.3 Abs. / Rel. FOM, Tot. Capt. ( 1 /-) s 3.1E+04 / 0.75 3.9E+03 / 0.07 Abs. / Rel. FOM, Capt. 6.7 ev ( 1 /-) s 4.9E+02 / 0.53 4.8E+01 / 0.06

Effects of thermal motion on neutron transport (with TMS) On reaction probabilities: - Doppler-broadening of resolved and unresolved resonances - Increase in potential scattering at low energies - Special case: bound atoms with S(α,β) tables On collision dynamics: - Secondary particle distributions of elastic scattering. - Secondary particle distributions of bound-atom scattering. With the current TMS methodology, - Red effects must still be pre-calculated - Blue effects can be taken into account on-the-fly.

Howto? TMS is only available in Serpent 2. Standard temperature treatment in multi-physics interface and fuel temperature feedback features. Manual use is similar to the Doppler pre-processor: - TMP = Use pre-processor - TMS = Use TMS treatment between smallest and largest nuclide temperature mat fuel1 6.7402E-02 tmp 669 mat fuel1 6.7402E-02 tms 669 92235.06c 9.3472E-04 92235.06c 9.3472E-04 92238.06c 2.1523E-02 92238.06c 2.1523E-02 8016.06c 4.4935E-02 8016.06c 4.4935E-02

Conclusions and future work TMS method is now fully functional in Serpent 2. It is about as fast as it gets, as long as all the nuclides are treated as temperature dependent. - Using a temperature independent lumped model for less-important fission products will be the next significant optimization step. TMS can be extended to unresolved energy region. (not yet demonstrated) Extension of the TMS idea to S(α,β) turned out to be very complicated Thermal scattering has to be handled by other means (not yet implemented, unfortunately)

Thank you for your attention! Questions? tuomas.viitanen@vtt.fi http://montecarlo.vtt.fi

References [1] V.N. OGIBIN, A.I. ORLOV, Majorized Cross-section Method for Tracking Neutrons in Moving Media, J. Nuclear Science and Technology, Methods and Codes for Mathematical Physics Series, 2(16), pp.6 9 (1984). [2] T. Viitanen and J. Leppänen, Explicit treatment of thermal motion in continuous-energy Monte Carlo tracking routines, Nucl. Sci. Eng., 171, 165-173 (2012). [3] T. Viitanen and J. Leppänen, Explicit temperature treatment in Monte Carlo neutron tracking routines First results. In proc. PHYSOR 2012, Knoxville, TN, Apr. 15-20, (2012). [4] T. Viitanen and J. Leppänen, Optimizing the implementation of the target motion sampling temperature treatment technique How fast can it get?, In proc. M&C 2013, Sun Valley, ID, May 5-9, (2013). [5] T. Viitanen and J. Leppänen, Target motion sampling temperature treatment technique with elevated basis cross section temperatures., Nucl. Sci. Eng., 177, 77-89 (2014). [6] T. Viitanen and J. Leppänen, Temperature majorant cross sections in Monte Carlo neutron neutron tracking, Nucl. Sci. Eng., Accepted for publication on Aug 31. 2014. [7] T. Viitanen and J. Leppänen, Effect of the Target Motion Sampling Temperature Treatment Method on the Statistics and Performance, Ann. Nucl. Energy, accepted, in-press.