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

Silva Kalcheva; Geert Van den Branden; Steven Van Dyck; Sven Van den Berghe; Gregory K. Housley; Nicolas E. Woolstenhulme; Irina Glagolenko; James I. Cole

doi:10.1016/j.anucene.2018.12.015

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

Silva Kalcheva, Geert Van den Branden, Steven Van Dyck, Sven Van den Berghe, Gregory K. Housley, Nicolas E. Woolstenhulme, Irina Glagolenko, James I. Cole

Reactor Control and Experiments

Research output › peer-review

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’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.

Original language	English
Pages (from-to)	303-318
Number of pages	16
Journal	Annals of nuclear energy
Volume	127
DOIs	https://doi.org/10.1016/j.anucene.2018.12.015
State	Published - 21 Dec 2018

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Cite this

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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.}",

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year = "2018",

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doi = "10.1016/j.anucene.2018.12.015",

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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.

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Y1 - 2018/12/21

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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

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DO - 10.1016/j.anucene.2018.12.015

M3 - Article

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JF - Annals of nuclear energy

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