Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO)

Research output: ThesisMaster's thesis

Standard

Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO). / Mylonakis, Antonios; Jaluvka, David (Peer reviewer).

Mol, Belgium : BNEN - Belgian Nuclear Higher Education Network, 2013. 102 p.

Research output: ThesisMaster's thesis

Harvard

Mylonakis, A & Jaluvka, D 2013, 'Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO)', BNEN - Belgian Nuclear Higher Education Network, Mol, Belgium.

APA

Mylonakis, A., & Jaluvka, D. (2013). Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO). Mol, Belgium: BNEN - Belgian Nuclear Higher Education Network.

Vancouver

Mylonakis A, Jaluvka D. Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO). Mol, Belgium: BNEN - Belgian Nuclear Higher Education Network, 2013. 102 p.

Author

Mylonakis, Antonios ; Jaluvka, David. / Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO). Mol, Belgium : BNEN - Belgian Nuclear Higher Education Network, 2013. 102 p.

Bibtex - Download

@phdthesis{0f6358b8ccb94cb3a6efa7937e2a8b23,
title = "Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO)",
abstract = "Currently, the advanced nuclear irradiation facility MYRRHA is under development at SCK•CEN. A special effort is being made to develop an in-core fuel management tool. This tool will use the stochastic metaheuristic optimization methods for solving the ICFMO problem which is characterized by the need to examine many feasible core configurations (loading patterns). Since each ICFMO problem requires the examination of a great number of different core loading patterns, something that is typically done by a standard reactor analysis code, it makes the stochastic optimization computationally burdensome. This work investigates the suitability of the use of the current version of SCALE, SCALE6.1, by the ICFMO tool, with function to examine the neutronic characteristics of a very simplified MYRRHA core model, used with purpose to reduce the computational time. This investigation examines the accuracy of the neutronic characteristics of MYRRHA calculated with SCALE6.1 and if the different SCALE6.1 modules’ computational time can be as short as it is required by the strict computational time limits that the stochastic ICFMO imposes",
keywords = "MYRRHA, SCALE, ICFMO, KENO, irradiation, in-core fuel",
author = "Antonios Mylonakis and David Jaluvka",
note = "Score = 2",
year = "2013",
month = "1",
day = "31",
language = "English",
publisher = "BNEN - Belgian Nuclear Higher Education Network",
school = "BNEN - Belgian Nuclear Higher Education Network",

}

RIS - Download

TY - THES

T1 - Modeling of MYRRHA core using SCALE6 for the purpose of the in-core fuel management optimization (ICFMO)

AU - Mylonakis, Antonios

A2 - Jaluvka, David

N1 - Score = 2

PY - 2013/1/31

Y1 - 2013/1/31

N2 - Currently, the advanced nuclear irradiation facility MYRRHA is under development at SCK•CEN. A special effort is being made to develop an in-core fuel management tool. This tool will use the stochastic metaheuristic optimization methods for solving the ICFMO problem which is characterized by the need to examine many feasible core configurations (loading patterns). Since each ICFMO problem requires the examination of a great number of different core loading patterns, something that is typically done by a standard reactor analysis code, it makes the stochastic optimization computationally burdensome. This work investigates the suitability of the use of the current version of SCALE, SCALE6.1, by the ICFMO tool, with function to examine the neutronic characteristics of a very simplified MYRRHA core model, used with purpose to reduce the computational time. This investigation examines the accuracy of the neutronic characteristics of MYRRHA calculated with SCALE6.1 and if the different SCALE6.1 modules’ computational time can be as short as it is required by the strict computational time limits that the stochastic ICFMO imposes

AB - Currently, the advanced nuclear irradiation facility MYRRHA is under development at SCK•CEN. A special effort is being made to develop an in-core fuel management tool. This tool will use the stochastic metaheuristic optimization methods for solving the ICFMO problem which is characterized by the need to examine many feasible core configurations (loading patterns). Since each ICFMO problem requires the examination of a great number of different core loading patterns, something that is typically done by a standard reactor analysis code, it makes the stochastic optimization computationally burdensome. This work investigates the suitability of the use of the current version of SCALE, SCALE6.1, by the ICFMO tool, with function to examine the neutronic characteristics of a very simplified MYRRHA core model, used with purpose to reduce the computational time. This investigation examines the accuracy of the neutronic characteristics of MYRRHA calculated with SCALE6.1 and if the different SCALE6.1 modules’ computational time can be as short as it is required by the strict computational time limits that the stochastic ICFMO imposes

KW - MYRRHA

KW - SCALE

KW - ICFMO

KW - KENO

KW - irradiation

KW - in-core fuel

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_127505

M3 - Master's thesis

PB - BNEN - Belgian Nuclear Higher Education Network

CY - Mol, Belgium

ER -

ID: 94853