FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE

The CANDLE Reactor (Constant Axial Shape of Neutron Flux, Nuclide Densities, and Power Profile during the Life of Energy Production) is a Generation IV reactor with a unique fuel-burning pattern resembling a candle that burns from the top down or vice versa. This reactor can operate using natural...

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Main Author: Afifah, Maryam
Format: Dissertations
Language:Indonesia
Online Access:https://digilib.itb.ac.id/gdl/view/87087
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Institution: Institut Teknologi Bandung
Language: Indonesia
id id-itb.:87087
spelling id-itb.:870872025-01-13T08:02:44ZFULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE Afifah, Maryam Indonesia Dissertations Neutronic, burnup, lead cooled fast reactor, MCNP6, Monte Carlo, CANDLE reactor INSTITUT TEKNOLOGI BANDUNG https://digilib.itb.ac.id/gdl/view/87087 The CANDLE Reactor (Constant Axial Shape of Neutron Flux, Nuclide Densities, and Power Profile during the Life of Energy Production) is a Generation IV reactor with a unique fuel-burning pattern resembling a candle that burns from the top down or vice versa. This reactor can operate using natural uranium during the equilibrium state. At startup, the fuel composition is assumed to be based on the spent fuel from an APWR reactor. The objective of this research is to determine the initial fuel composition at startup to ensure the reactor remains critical until it reaches the equilibrium state, analyze various neutronic characteristics, and evaluate the effects of thermal power variation and core size on neutronic calculations. The reactor design was then optimized to achieve a lower excess reactivity compared to the initial design. Neutronic calculations were conducted using the Monte Carlo method with MCNP6, referencing the Evaluated Nuclear Data File (ENDF/B-VII.1). Preliminary results show that for core designs with thermal power variations from 400 MWth to 800 MWth, criticality can be maintained for 80 years of burnup . Burning wave velocity can be calculated from the shifting of power peak position for several thermal power core designs. After optimization, a minimum of 4 assembly layers with around 240 fuel pins per assembly was achieved. The optimized design resulted in reactivity below 2%. text
institution Institut Teknologi Bandung
building Institut Teknologi Bandung Library
continent Asia
country Indonesia
Indonesia
content_provider Institut Teknologi Bandung
collection Digital ITB
language Indonesia
description The CANDLE Reactor (Constant Axial Shape of Neutron Flux, Nuclide Densities, and Power Profile during the Life of Energy Production) is a Generation IV reactor with a unique fuel-burning pattern resembling a candle that burns from the top down or vice versa. This reactor can operate using natural uranium during the equilibrium state. At startup, the fuel composition is assumed to be based on the spent fuel from an APWR reactor. The objective of this research is to determine the initial fuel composition at startup to ensure the reactor remains critical until it reaches the equilibrium state, analyze various neutronic characteristics, and evaluate the effects of thermal power variation and core size on neutronic calculations. The reactor design was then optimized to achieve a lower excess reactivity compared to the initial design. Neutronic calculations were conducted using the Monte Carlo method with MCNP6, referencing the Evaluated Nuclear Data File (ENDF/B-VII.1). Preliminary results show that for core designs with thermal power variations from 400 MWth to 800 MWth, criticality can be maintained for 80 years of burnup . Burning wave velocity can be calculated from the shifting of power peak position for several thermal power core designs. After optimization, a minimum of 4 assembly layers with around 240 fuel pins per assembly was achieved. The optimized design resulted in reactivity below 2%.
format Dissertations
author Afifah, Maryam
spellingShingle Afifah, Maryam
FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
author_facet Afifah, Maryam
author_sort Afifah, Maryam
title FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
title_short FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
title_full FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
title_fullStr FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
title_full_unstemmed FULL CORE MODELLING OPTIMIZATION OF PB-BI COOLED CANDLE REACTOR FOR STARTUP AND EQUILIBRIUM STATE USING PARALLEL COMPUTATION MCNP6 CODE
title_sort full core modelling optimization of pb-bi cooled candle reactor for startup and equilibrium state using parallel computation mcnp6 code
url https://digilib.itb.ac.id/gdl/view/87087
_version_ 1822011259853209600