Advanced Nuclear Fuel Cycle Code Simulator with a Full Graphical - - PowerPoint PPT Presentation

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Advanced Nuclear Fuel Cycle Code Simulator with a Full Graphical - - PowerPoint PPT Presentation

Jan 28, 2024 540 likes •771 views

Advanced Nuclear Fuel Cycle Code Simulator with a Full Graphical interface Baej Chmielarz, Wacaw Gudowski, Torbjrn Bck, Karen Atabekjan, Alan Tkaczyk E-mail contacts: Blazej Chmielarz blazejc@kth.se Waclaw Gudowski waclaw@kth.se 1

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Advanced Nuclear Fuel Cycle Code Simulator with a Full Graphical interface

Błażej Chmielarz, Wacław Gudowski, Torbjörn Bäck, Karen Atabekjan, Alan Tkaczyk E-mail contacts:

Blazej Chmielarz blazejc@kth.se Waclaw Gudowski waclaw@kth.se

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Overview

  • 1. Introduction
  • 2. Technical features
  • 3. GUI
  • 4. Status
  • 5. Future plans

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Introduction

The idea behind the program: –Easy to use –With a GUI –Short runtime –Open-source –Learning and educating tool

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Technical features

  • Developed for Linux
  • Written in C++
  • Requires Boost, Grace and gtkmm 2.4

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Technical features

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Technical features

Solution method

– Burnup matrix, flux specific, 1307 nuclides – Reactor timesteps: 1 day, 5 days, 30 days, 1 year – Today´s status:

  • Includes today one PWR and one BWR design
  • Fixed flux (1014 for PWR and 5*1013) for BWR

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Technical features

Input

– Scenario file

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GUI

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GUI

Reactors change color when they start

  • perating in the

scenario

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GUI

‘New scenario’

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GUI

‘Edit Reactor’ ‘Edit Scenario‘

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GUI

‘Plot’

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GUI

‘Plot’

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Status

  • Functional

– No reprocessing, no MOX cycles implemented – Short runtime (under 5 minutes) – Instantaneous processing/infinite storage

  • Accepts MCNP output for calculation of burnup

matrix

  • Can be compiled on new Linux systems
  • Data is exported only to Grace, Open-sourcce

plotting tool

  • Not validated against other codes

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Future plans

  • Validation of a simple model with results from
  • ther codes
  • Implementation of new reactor designs using

cross sections from Serpent output

– In spirit of Open-source – Requires further validation – In development

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Future plans

  • Introduction of breeder reactors and ADS

– Requires validation of reprocessing and of breeding

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Future plans

  • Accurate calculation of flux using mass

balance:

– In order to find accurate BU matrix – Using 𝐹 = Δ𝑛𝑑2 flux can be determined – 𝐹 = 𝐹𝑠𝑏𝑒𝑗𝑏𝑢𝑗𝑝𝑜 + 𝐹

𝑔𝑗𝑡𝑡𝑗𝑝𝑜

– 𝐹

𝑔𝑗𝑡𝑡𝑗𝑝𝑜 = #𝑔𝑗𝑡𝑡𝑗𝑝𝑜 × 𝐹1 𝑔𝑗𝑡𝑡𝑗𝑝𝑜

– #𝑔𝑗𝑡𝑡𝑗𝑝𝑜 = 𝑔(𝑢, 𝑚, 𝑛, 𝜚, 𝜃, 𝑔, 𝑄

𝑂𝑀)

– 𝐹𝑠𝑏𝑒𝑗𝑏𝑢𝑗𝑝𝑜 ≈ 7%

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Future plans – flux calculation

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Future plans – flux calculation

  • Problems:

– 𝐹𝑠𝑓𝑏𝑑𝑢𝑝𝑠 = 𝐹𝑠𝑏𝑒𝑗𝑏𝑢𝑗𝑝𝑜 + 𝐹

𝑔𝑗𝑡𝑡𝑗𝑝𝑜 − 𝐹𝑚𝑝𝑡𝑡

– 𝐹𝑚𝑝𝑡𝑡 = 𝐹ℎ𝑓𝑏𝑢 + 𝐹𝑠𝑏𝑒𝑗𝑏𝑢𝑗𝑝𝑜 – 𝐹𝑠𝑏𝑒𝑗𝑏𝑢𝑗𝑝𝑜 ≠ 𝑑𝑝𝑜𝑡𝑢 – Requires iteration of calculating a burnup matrix which includes all possible nuclides, computationally expensive – In development

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Acknowledgment

  • This work is a part of the EU-project “Brilliant”

Project reference: 662167 and European Master in Innovative Nuclear Engineering – EMINE, KIC

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Thank you for your attention Questions?

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