Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor

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Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor. / Kalcheva, Silva; Van den Branden, Geert; Van Dyck, Steven; Van den Berghe, Sven; Housley, Gregory K.; Woolstenhulme, Nicolas E.; Glagolenko, Irina; Cole, James I.

In: Annals of nuclear energy, Vol. 127, 21.12.2018, p. 303-318.

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Kalcheva, Silva ; Van den Branden, Geert ; Van Dyck, Steven ; Van den Berghe, Sven ; Housley, Gregory K. ; Woolstenhulme, Nicolas E. ; Glagolenko, Irina ; Cole, James I. / Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor. In: Annals of nuclear energy. 2018 ; Vol. 127. pp. 303-318.

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@article{cbff0da84ff6481bbbaf7f6171086f2f,
title = "Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor",
abstract = "The BR2 reactor is involved in preliminary neutronics feasibility studies for irradiation of four Design Demonstration Element (DDE) tests foreseen in the US High Performance Research Reactor (USHPRR) conversion program: MURR, MITR, NBSR and HFIR. The purpose of the irradiation will be to qualify the new LEU fuel material for each DDE Lead Test Assembly in the BR2 reactor at conditions that are similar for the reactor of origin. The present paper focuses on the preliminary feasibility scenarios for simultaneous irradiation of two DDE{\textquoteright}s: the MITR and the NBSR Lead Test Assemblies in the BR2 reactor. The MITR and the NBSR fuel elements will be loaded in the 200 mm diameter channels (H5 and H3). In order to {\textquoteleft}mimic{\textquoteright} the irradiation conditions for each DDE in the BR2 reactor as in the original reactors, a number of optimization scenarios are considered. The flux and burn-up calculations are performed using the fully automatic option of the MCNP6/CINDER90 code.",
keywords = "MCNP6, NBSR, MITR, Conversion, LEU",
author = "Silva Kalcheva and {Van den Branden}, Geert and {Van Dyck}, Steven and {Van den Berghe}, Sven and Housley, {Gregory K.} and Woolstenhulme, {Nicolas E.} and Irina Glagolenko and Cole, {James I.}",
note = "Score=10",
year = "2018",
month = dec,
day = "21",
doi = "10.1016/j.anucene.2018.12.015",
language = "English",
volume = "127",
pages = "303--318",
journal = "Annals of nuclear energy",
issn = "0306-4549",
publisher = "Elsevier",

}

RIS - Download

TY - JOUR

T1 - Feasibility studies for simultaneous irradiation of NBSR & MITR fuelelements in the BR2 reactor

AU - Kalcheva, Silva

AU - Van den Branden, Geert

AU - Van Dyck, Steven

AU - Van den Berghe, Sven

AU - Housley, Gregory K.

AU - Woolstenhulme, Nicolas E.

AU - Glagolenko, Irina

AU - Cole, James I.

N1 - Score=10

PY - 2018/12/21

Y1 - 2018/12/21

N2 - The BR2 reactor is involved in preliminary neutronics feasibility studies for irradiation of four Design Demonstration Element (DDE) tests foreseen in the US High Performance Research Reactor (USHPRR) conversion program: MURR, MITR, NBSR and HFIR. The purpose of the irradiation will be to qualify the new LEU fuel material for each DDE Lead Test Assembly in the BR2 reactor at conditions that are similar for the reactor of origin. The present paper focuses on the preliminary feasibility scenarios for simultaneous irradiation of two DDE’s: the MITR and the NBSR Lead Test Assemblies in the BR2 reactor. The MITR and the NBSR fuel elements will be loaded in the 200 mm diameter channels (H5 and H3). In order to ‘mimic’ the irradiation conditions for each DDE in the BR2 reactor as in the original reactors, a number of optimization scenarios are considered. The flux and burn-up calculations are performed using the fully automatic option of the MCNP6/CINDER90 code.

AB - The BR2 reactor is involved in preliminary neutronics feasibility studies for irradiation of four Design Demonstration Element (DDE) tests foreseen in the US High Performance Research Reactor (USHPRR) conversion program: MURR, MITR, NBSR and HFIR. The purpose of the irradiation will be to qualify the new LEU fuel material for each DDE Lead Test Assembly in the BR2 reactor at conditions that are similar for the reactor of origin. The present paper focuses on the preliminary feasibility scenarios for simultaneous irradiation of two DDE’s: the MITR and the NBSR Lead Test Assemblies in the BR2 reactor. The MITR and the NBSR fuel elements will be loaded in the 200 mm diameter channels (H5 and H3). In order to ‘mimic’ the irradiation conditions for each DDE in the BR2 reactor as in the original reactors, a number of optimization scenarios are considered. The flux and burn-up calculations are performed using the fully automatic option of the MCNP6/CINDER90 code.

KW - MCNP6

KW - NBSR

KW - MITR

KW - Conversion

KW - LEU

UR - http://ecm.sckcen.be/OTCS/llisapi.dll/open/35528259

U2 - 10.1016/j.anucene.2018.12.015

DO - 10.1016/j.anucene.2018.12.015

M3 - Article

VL - 127

SP - 303

EP - 318

JO - Annals of nuclear energy

JF - Annals of nuclear energy

SN - 0306-4549

ER -

ID: 5605319