Modeling and Simulation Approaches to Challenges in Nuclear Energy – to Challenges in Nuclear Energy – Kathryn Huff

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Modeling and Simulation Approaches to Challenges in Nuclear Energy – to Challenges in Nuclear Energy – Kathryn Huff

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2016-01-19-uta

research seminar at UT Austin

On Github katyhuff / 2016-01-19-uta

Modeling and Simulation Approaches

to Challenges in Nuclear Energy

Kathryn Huff

University of Texas at Austin

January 19, 2016

Insights at Disparate Scales

PB-FHR Fuel Geometry

Coupled Multi-Physics Analysis

Severe accident neutronics and thermal hydraulics can be simulated beautifully for simple geometries and well studied materials. (below, INL BISON work.)

FHR, Accident Transient Analysis

  • Collect experimental data
  • Conduct algebraic, static, and benchmark simulations
  • Develop 0D coupled neutronics/TH model (PyRK)
  • Develop 3D neutronics/TH model
  • Compare 0D and 3D simulations
  • Couple additional physics (e.g. fuel performance)
PyRK: Python for Reactor Kinetics

Review of Nuclear Reactor Kinetics

\[\sigma(E,\vec{r},\hat{\Omega},T,x,i)\]

\[k=1\]

Reactivity

\[ \begin{align} k &= \mbox{"neutron multiplication factor"}\\ &= \frac{\mbox{neutrons causing fission}}{\mbox{neutrons produced by fission}}\\ \rho &= \frac{k-1}{k}\\ \rho &= \mbox{reactivity}\\ \end{align} \]

\[\beta_i, \lambda_{d,i}\]

PyRK

  • 6-precursor-group,
  • 11-decay-group Point Reactor Kinetics model
  • Lumped Parameter thermal hydraulics model
  • Object-oriented, geometry and material agnostic framework

Point Reactor Kinetics

\[ \begin{align} p &= \mbox{ reactor power }\\ \rho(t,&T_{fuel},T_{cool},T_{mod}, T_{refl}) = \mbox{ reactivity}\\ \beta &= \mbox{ fraction of neutrons that are delayed}\\ \beta_j &= \mbox{ fraction of delayed neutrons from precursor group j}\\ \zeta_j &= \mbox{ concentration of precursors of group j}\\ \lambda_{d,j} &= \mbox{ decay constant of precursor group j}\\ \Lambda &= \mbox{ mean generation time }\\ \omega_k &= \mbox{ decay heat from FP group k}\\ \kappa_k &= \mbox{ heat per fission for decay FP group k}\\ \lambda_{FP,k} &= \mbox{ decay constant for decay FP group k}\\ T_i &= \mbox{ temperature of component i} \end{align} \]
\[ \frac{d}{dt}\left[ \begin{array}{c} p\\ \zeta_1\\ .\\ \zeta_j\\ .\\ \zeta_J\\ \omega_1\\ .\\ \omega_k\\ .\\ \omega_K\\ T_{i}\\ .\\ T_{I}\\ \end{array} \right] = \left[ \begin{array}{ c } \frac{\rho(t,T_{i},\cdots)-\beta}{\Lambda}p + \displaystyle\sum^{j=J}_{j=1}\lambda_{d,j}\zeta_j\\ \frac{\beta_1}{\Lambda} p - \lambda_{d,1}\zeta_1\\ .\\ \frac{\beta_j}{\Lambda}p-\lambda_{d,j}\zeta_j\\ .\\ \frac{\beta_J}{\Lambda}p-\lambda_{d,J}\zeta_J\\ \kappa_1p - \lambda_{FP,1}\omega_1\\ .\\ \kappa_kp - \lambda_{FP,k}\omega_k\\ .\\ \kappa_{k p} - \lambda_{FP,k}\omega_{k}\\ f_{i}(p, C_{p,i}, T_{i}, \cdots)\\ .\\ f_{I}(p, C_{p,I}, T_{I}, \cdots)\\ \end{array} \right] \]

Lumped Parameter Heat Transfer

The heat flow out of body $i$ is the sum of surface heat flow by conduction, convection, radiation, and other mechanisms to each adjacent body, $j$: \[ \begin{align} Q &= Q_i + \sum_j Q_{ij}\\ &=Q_i + \sum_j\frac{T_{i} - T_{j}}{R_{th,ij}}\\ \dot{Q} &= \mbox{total heat flow out of body i }[J\cdot s^{-1}]\\ Q_i &= \mbox{other heat transfer, a constant }[J\cdot s^{-1}]\\ T_i &= \mbox{temperature of body i }[K]\\ T_j &= \mbox{temperature of body j }[K]\\ j &= \mbox{adjacent bodies }[-]\\ R_{th} &= \mbox{thermal resistence of the component }[K \cdot s \cdot J^{-1}]. \end{align} \]

Quality Control

Unit Checking

In PyRK, the Pint package (pint.readthedocs.org/en/0.6/) is used keeping track of units, converting between them, and throwing errors when unit conversions are not sane.

Version Control

Keeping track of versions of the code makes it possible to experiment without fear and placing the code online encourages use and collaboration.

Automated Documentation

Automated documentation creates a browsable website explaining the most recent version of the code.

Test Suite

The classes and functions that make up the code are tested individually for robustness using nose.

Continuous Integration

The tests are run every time a change is made to the repository online. The results are public. If a main branch has a failed test, I get an email.

PB-FHR Reactivity Insertion

Pebble-Bed, Fluoride Salt Cooled, High-Temperature Reactor
  • Molten FLiBe Coolant
  • Annular Core
  • Annular Pebble Fuel
  • Steady Inlet Temperature
  • Ramp Reactivity Insertion, 600pcm over 10s

Ramp Reactivity Insertion

Ramp Reactivity Insertion

# External Reactivity
from reactivity_insertion import RampReactivityInsertion
rho_ext = RampReactivityInsertion(timer=ti,
                                  t_start=t_feedback + 10.0*units.seconds,
                                  t_end=t_feedback + 20.0*units.seconds,
                                  rho_init=0.0*units.delta_k,
                                  rho_rise=600.0*units.pcm,
                                  rho_final=600.0*units.pcm)

Components


fuel = th.THComponent(name="fuel",
                      mat=TRISO(),
                      vol=vol_fuel,
                      T0=t_fuel,
                      alpha_temp=alpha_fuel,
                      timer=ti,
                      heatgen=True,
                      power_tot=power_tot/n_pebbles,
                      sph=True,
                      ri=r_mod,
                      ro=r_fuel
                      )

mod = th.THComponent(name="mod",
                     mat=Graphite(),
                     vol=vol_mod,
                     T0=t_mod,
                     alpha_temp=alpha_mod,
                     timer=ti,
                     sph=True,
                     ri=0.0,
                     ro=r_mod)

cool = th.THComponent(name="cool",
                      mat=Flibe(),
                      vol=vol_cool,
                      T0=t_cool,
                      alpha_temp=alpha_cool,
                      timer=ti)

shell = th.THComponent(name="shell",
                       mat=Graphite(),
                       vol=vol_shell,
                       T0=t_shell,
                       alpha_temp=alpha_shell,
                       timer=ti,
                       sph=True,
                       ri=r_fuel,
                       ro=r_shell)

Heat Transfer

# The coolant convects to the pebbles
cool.add_convection('pebble', h=h_cool, area=a_pb)
cool.add_advection('cool', m_flow/n_pebbles, t_inlet, cp=cool.cp)

Ramp Reactivity Insertion

Fuel Layer Temperature

Coolant Temperature

A Nuclear Fuel Cycle Simulation Framework

The Nuclear Fuel Cycle

Hundreds of discrete facilities mine, mill, convert, fabricate, transmute, recycle, and store nuclear material.

Fuel Cycle Metrics

  • Mass Flow
    • inventories, decay heat, radiotoxicity,
    • proliferation resistance and physical protection (PRPP) indices.
  • Cost
    • levelized cost of electricity,
    • facility life cycle costs.
  • Economics
    • power production, facility deployments,
    • dynamic pricing and feedback.
  • Disruptions
    • reliability, safety,
    • system robustness.

Current Simulators

  • CAFCA (MIT)
  • COSI (CEA)
  • DANESS (ANL)
  • DESAE (Rosatom)
  • Evolcode (CIEMAT)
  • FAMILY (IAEA)
  • GENIUSv1 (INL)
  • GENIUS v2 (UW)
  • NFCSim (LANL)
  • NFCSS (IAEA)
  • NUWASTE (NWTRB)
  • ORION (NNL)
  • MARKAL (BNL)
  • VISION (INL)

State of the Art

Performance

  • Speed interactive time scales
  • Fidelity: detail commensurate with existing challenges
  • Detail: discrete material and agent tracking
  • Regional Modeling: enabling international socio-economics

Beyond the State of the Art

Access

  • Openness: for collaboration, validation, and code sustainability.
  • Usability: for a wide range of user sophistication

Extensibility

  • Modularity: core infrastructure independent of proprietary or sensitive data and models
  • Flexibility with a focus on robustness for myriad potential developer extensions.

Extensibility

Openness

Growing Ecosystem

...Well Beyond

Algorithmic Sophistication

  • Efficient: memory-efficient isotope tracking
  • Customizable: constrained fuel supply
  • Dynamic: isotopic-quality-based resource routing
  • Physics-based: fuel fungibility

Agent Based Systems Analysis

An agent-based simulation is made up of actors and communications between those actors.

Agent Based Systems Analysis

A facility might create material.

Agent Based Systems Analysis

It might request material.

Agent Based Systems Analysis

It might do both.

Agent Based Systems Analysis

Even simple fuel cycles have many independent agents.

Dynamic Resource Exchange

\[N_i \subset N\]

Dynamic Resource Exchange

\[N_j \subset N\]

Dynamic Resource Exchange

\[N_i \cup N_j = N\]

Feasibility vs. Optimization

If a decision problem is in NP-C, then the corresponding optimization problem is NP-hard.

Multi-Commodity Transportation Formulation

Multi-Commodity Transportation Formulation

\[ \begin{align} \min_{x} z &= \sum_{i\in I}\sum_{j\in J} c_{i,j}x_{i,j} & \\ s.t & \sum_{i\in I_s}\sum_{j\in J} a_{i,j}^k x_{i,j} \le b_s^k & \forall k\in K_s, \forall s\in S\\ & \sum_{J\in J_r}\sum_{i\in I} a_{i,j}^k x_{i,j} \le b_r^k & \forall k\in K_r, \forall r\in R\\ & x_{i,j} \in [0,x_j] & \forall i\in I, \forall j\in J \end{align} \]

Dynamic Resource Exchange

Dynamic Resource Exchange

Dynamic Resource Exchange

   mox
-    waste
+    spent_fuelmox_fresh_fuelmox_spent_fuel

Dynamic Resource Exchange

Transition Analysis

  • LWR to SFR
  • $T_0 = 2015$
  • $T_f <= 2215$
  • $C_0 = 100$ GWe LWR
  • Annual nuclear energy demand growth: 1%
  • Legacy LWRs have either 60-year lifetimes or 80-year lifetimes.
  • Spent LWR fuel reprocessed to fabricate FR fuel
  • Spent FR fuel reprocessed to fabricate FR fuel

Transition Analysis

Power generated by reactor type.

Transition Analysis

Capacity deployed each year, by reactor type.

Insights at Disparate Scales

Detailed Metrics

Material Attractiveness

Insights at Disparate Scales

Links

Acknowledgements

  • Denia Djokic
  • Matthew Gidden
  • Massimiliano Fratoni
  • Ehud Greenspan
  • Per Peterson
  • Anthony Scopatz
  • Xin Wang
  • Paul Wilson
  • Jasmina Vujic
  • and many more...

THE END

Katy Huff

katyhuff.github.io/2016-01-19-uta Modeling and Simulation Approaches to Challenges in Nuclear Energy by Kathryn Huff is licensed under a Creative Commons Attribution 4.0 International License.Based on a work at http://katyhuff.github.io/2016-01-19-uta.
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