The H.B. Robinson Unit 2 (HBR-2) Pressure Vessel Dosimetry Benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The HBR-2 analysis in the SINBAD database consisted in using the two-dimensional (2D) discrete ordinates (SN) code DORT and the flux synthesis method. The goals of the present work were to perform three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed HBR-2 3D geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as the ENEA-Bologna BUGJEFF311.BOLIB and BUGENDF70.BOLIB libraries and the ORNL BUGLE-B7 library as well. All the cited libraries, BUGLE-96 included, were alternatively used in the calculations and the related results are here reported and compared on both (X,Y,Z) and (R,,Z) geometries. This document is a summary of the analysis thoroughly described in ENEA-Bologna SICNUC-P9H6-003 and contains some information omitted in such a report.

H.B. Robinson-2 Pressure Vessel Dosimetry Benchmark: Summary of ENEA-Bologna Three-Dimensional Deterministic Analyses

Orsi, Roberto
2019-03-25

Abstract

The H.B. Robinson Unit 2 (HBR-2) Pressure Vessel Dosimetry Benchmark is an in- and ex-Reactor Pressure Vessel (RPV) neutron dosimetry benchmark based on experimental data from the HBR-2 reactor, a 2300-MW PWR designed by Westinghouse and put in operation in March 1971, openly available through the SINBAD Database at OECD/NEA data Bank. The HBR-2 analysis in the SINBAD database consisted in using the two-dimensional (2D) discrete ordinates (SN) code DORT and the flux synthesis method. The goals of the present work were to perform three-dimensional (3D) fixed source transport calculations in both Cartesian (X,Y,Z) and cylindrical (R,,Z) geometries by using the TORT-3.2 discrete ordinates code on very detailed HBR-2 3D geometrical models and to test the latest broad-group coupled (47 neutron groups + 20 photon groups) working cross section libraries in FIDO-ANISN format with same structure as BUGLE-96, such as the ENEA-Bologna BUGJEFF311.BOLIB and BUGENDF70.BOLIB libraries and the ORNL BUGLE-B7 library as well. All the cited libraries, BUGLE-96 included, were alternatively used in the calculations and the related results are here reported and compared on both (X,Y,Z) and (R,,Z) geometries. This document is a summary of the analysis thoroughly described in ENEA-Bologna SICNUC-P9H6-003 and contains some information omitted in such a report.
Fisica dei reattori nucleari;Dati nucleari;Fisica nucleare;Rapporto tecnico
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Utilizza questo identificativo per citare o creare un link a questo documento: http://hdl.handle.net/20.500.12079/8099
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