TY - RPRT
TI - DOT 3.5-E (DOT 3.5-E/JEF-1) analysis of the PCA-Replica (H2O/FE) shielding benchmark for the LWR-PV damage prediction
AB - The results of a DOT 3.5-E/JEF-1 validation on the (H2O/Fr) PCA-REPLICA (UKAEA-Winfith) low-flux shielding benchmark are presented. The PCA-REPLICA experiments reproduces the excore radial geometry of a PWR and is closely related to LWR safety since it is dedicated to test the accuracy of the calculated neutron exposure parameters (fast fluence and iron displacement rates) in a pressure vessel simulator. The NJOY/THEMIS data processing system is employed to obtain the neutron damage-energy cross sections for the JEF-1 iron file. The SN 1-D ANISN code is used to collapse cross sections from the VITAMIN-J (175 n) shielding library, based on the JEF-1 data, to a 28 group working library for 2-D calculations. A 3-D-equivalent synthesis (X,Y,Z) of 2-D and 1-D DOT 3.5-E SN calculations in a plane geometry, gives the integral and spectral results for comparison with the respective experimental data. The underprediction of the in-vessel dosimeter experimental activities depends probably on an overestimation of the iron inelastic scattering cross section of the JEF-1 file.
AU - Pescarini, M [ENEA, Bologna (Italy)]
KW - 36 MATERIALS SCIENCE
KW - 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
KW - 42 ENGINEERING
KW - PWR TYPE REACTORS
KW - DAMAGING NEUTRON FLUENCE
KW - PRESSURE VESSELS
KW - BENCHMARKS
KW - D CODES
KW - FAST NEUTRONS
KW - NEUTRON TRANSPORT
KW - REACTOR SAFETY
KW - SHIELDING
KW - 360106
KW - 210200
KW - 420500
KW - RADIATION EFFECTS
KW - POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED
KW - MATERIALS TESTING
DO -
UR -
PB -
CY - Italy
PY - 1991
DA - 1992-12-31
LA - English
J2 -
C1 - ENEA, Rome (Italy)
C2 -
ER -