H.B. Robinson Unit 2 (HBR-2) is a 2300-MW (thermal) pressurized light-water reactor (PWR) designed by Westinghouse, placed in operation in March 1971. The HBR-2 Pressure Vessel Dosimetry Benchmark, based on experimental data from an operating PWR reactor, is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark openly available through the SINBAD Database at the OECD/NEA data Bank. Analysis of the HBR-2 benchmark can be used as partial fulfillment of the requirements for the qualification of the methodology for calculating neutron fluence in RPVs, as required by the U.S. Nuclear Regulatory Guide 1.190. This report describes the three-dimensional (3D) fixed source transport calculations performed in both Cartesian (X,Y,Z) and cylindrical (R,Θ,Z) geometries with the TORT-3.2 discrete ordinates (SN) code on detailed HBR-2 (up to the biological shield) geometrical models, prepared by using the ENEA-Bologna BOT3P-5.3 code system. The ENEA-Bologna BUGJEFF311.BOLIB and BUGENDF70.BOLIB broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format and the similar ORNL BUGLE-B7 and BUGLE-96 libraries were alternatively used in the calculations. The calculated to measured specific activities (C/M) at the end of reactor fuel cycle 9 in both the surveillance capsule and the reactor cavity were obtained and are here reported. The agreement between calculated and measured results was satisfactory.

H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark - Deterministic Analysis in Both Cartesian (X,Y,Z) and Cylindrical (R,Θ,Z) Geometries Using the TORT-3.2 3D Transport Code, the BUGJEFF311.BOLIB, BUGENDF70.BOLIB, BUGLE-B7 and the BUGLE-96 Cross Section Libraries

Orsi, Roberto
2019

Abstract

H.B. Robinson Unit 2 (HBR-2) is a 2300-MW (thermal) pressurized light-water reactor (PWR) designed by Westinghouse, placed in operation in March 1971. The HBR-2 Pressure Vessel Dosimetry Benchmark, based on experimental data from an operating PWR reactor, is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark openly available through the SINBAD Database at the OECD/NEA data Bank. Analysis of the HBR-2 benchmark can be used as partial fulfillment of the requirements for the qualification of the methodology for calculating neutron fluence in RPVs, as required by the U.S. Nuclear Regulatory Guide 1.190. This report describes the three-dimensional (3D) fixed source transport calculations performed in both Cartesian (X,Y,Z) and cylindrical (R,Θ,Z) geometries with the TORT-3.2 discrete ordinates (SN) code on detailed HBR-2 (up to the biological shield) geometrical models, prepared by using the ENEA-Bologna BOT3P-5.3 code system. The ENEA-Bologna BUGJEFF311.BOLIB and BUGENDF70.BOLIB broad-group coupled (47 n + 20 γ) working cross section libraries in FIDO-ANISN format and the similar ORNL BUGLE-B7 and BUGLE-96 libraries were alternatively used in the calculations. The calculated to measured specific activities (C/M) at the end of reactor fuel cycle 9 in both the surveillance capsule and the reactor cavity were obtained and are here reported. The agreement between calculated and measured results was satisfactory.
Fisica nucleare;Fisica dei reattori nucleari;Dati nucleari;Rapporto tecnico
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/20.500.12079/8092
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