Research output: Contribution to journal › Article › peer-review
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.Research output: Contribution to journal › Article › peer-review
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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