Transient analysis of the control/safety rods injection in MYRRHA after a power excursion incident

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Transient analysis of the control/safety rods injection in MYRRHA after a power excursion incident. / Vervecken, Lieven; Aït Abderrahim, Hamid (Peer reviewer).

Mol, Belgium : BNEN - Belgian Nuclear Higher Education Network, 2011. 82 p.

Research output: ThesisMaster's thesis

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@phdthesis{1c47c7f08f7644c2bf9c3089f2ea30a7,
title = "Transient analysis of the control/safety rods injection in MYRRHA after a power excursion incident",
abstract = "MYRRHA is a fast-spectrum irradiation facility to be constructed at SCK-CEN in Mol, Belgium. It is being designed to be operated in both sub-critical mode (coupled to a proton accelerator) as well as critical mode. In the latter mode, control rods and safety rods ensure the reactivity control and safety of the reactor. In order to support the safety file of MYRRA, one needs to prove that the insertion of a certain amount of anti-reactivity indeed stops the excursion but also limits damage to fuel pellets and fuel cladding. This means that a transient analysis of this power excursion incident followed by the insertion (with a certain time delay and fall time) of the control/safety rods needs to be performed with as a result the temperature evolution in time for the fuel pellet and fuel cladding. This will allow to judge whether the currently foreseen control/safety rod system has indeed a sufficient amount of anti-reactivity and if this anti-reactivity can be inserted fast enough. The analysis can be done by both SITHER, a single channel time-dependent code, and/or RELAP, a well-known systems code",
keywords = "MYRRHA, RELAP, safety rod",
author = "Lieven Vervecken and {A{\"i}t Abderrahim}, Hamid",
note = "Score=10",
year = "2011",
month = "8",
language = "English",
publisher = "BNEN - Belgian Nuclear Higher Education Network",
school = "BNEN - Belgian Nuclear Higher Education Network",

}

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TY - THES

T1 - Transient analysis of the control/safety rods injection in MYRRHA after a power excursion incident

AU - Vervecken, Lieven

A2 - Aït Abderrahim, Hamid

N1 - Score=10

PY - 2011/8

Y1 - 2011/8

N2 - MYRRHA is a fast-spectrum irradiation facility to be constructed at SCK-CEN in Mol, Belgium. It is being designed to be operated in both sub-critical mode (coupled to a proton accelerator) as well as critical mode. In the latter mode, control rods and safety rods ensure the reactivity control and safety of the reactor. In order to support the safety file of MYRRA, one needs to prove that the insertion of a certain amount of anti-reactivity indeed stops the excursion but also limits damage to fuel pellets and fuel cladding. This means that a transient analysis of this power excursion incident followed by the insertion (with a certain time delay and fall time) of the control/safety rods needs to be performed with as a result the temperature evolution in time for the fuel pellet and fuel cladding. This will allow to judge whether the currently foreseen control/safety rod system has indeed a sufficient amount of anti-reactivity and if this anti-reactivity can be inserted fast enough. The analysis can be done by both SITHER, a single channel time-dependent code, and/or RELAP, a well-known systems code

AB - MYRRHA is a fast-spectrum irradiation facility to be constructed at SCK-CEN in Mol, Belgium. It is being designed to be operated in both sub-critical mode (coupled to a proton accelerator) as well as critical mode. In the latter mode, control rods and safety rods ensure the reactivity control and safety of the reactor. In order to support the safety file of MYRRA, one needs to prove that the insertion of a certain amount of anti-reactivity indeed stops the excursion but also limits damage to fuel pellets and fuel cladding. This means that a transient analysis of this power excursion incident followed by the insertion (with a certain time delay and fall time) of the control/safety rods needs to be performed with as a result the temperature evolution in time for the fuel pellet and fuel cladding. This will allow to judge whether the currently foreseen control/safety rod system has indeed a sufficient amount of anti-reactivity and if this anti-reactivity can be inserted fast enough. The analysis can be done by both SITHER, a single channel time-dependent code, and/or RELAP, a well-known systems code

KW - MYRRHA

KW - RELAP

KW - safety rod

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/ezp_123806

M3 - Master's thesis

PB - BNEN - Belgian Nuclear Higher Education Network

CY - Mol, Belgium

ER -

ID: 383723