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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

Technical Report:

Abstract

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.
Authors:
Pescarini, M [1] 
  1. ENEA, Bologna (Italy)
Publication Date:
Dec 31, 1991
Product Type:
Technical Report
Report Number:
ENEA-RT-INN-90-21
Reference Number:
SCA: 360106; 210200; 420500; PA: AIX-23:007024; SN: 92000619377
Resource Relation:
Other Information: PBD: 1991
Subject:
36 MATERIALS SCIENCE; 21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; 42 ENGINEERING; PWR TYPE REACTORS; DAMAGING NEUTRON FLUENCE; PRESSURE VESSELS; BENCHMARKS; D CODES; FAST NEUTRONS; NEUTRON TRANSPORT; REACTOR SAFETY; SHIELDING; 360106; 210200; 420500; RADIATION EFFECTS; POWER REACTORS, NONBREEDING, LIGHT-WATER MODERATED, NONBOILING WATER COOLED; MATERIALS TESTING
OSTI ID:
10104081
Research Organizations:
ENEA, Rome (Italy)
Country of Origin:
Italy
Language:
English
Other Identifying Numbers:
Other: ON: DE92612562; TRN: IT9100010007024
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
75 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Pescarini, M. 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. Italy: N. p., 1991. Web.
Pescarini, M. 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. Italy.
Pescarini, M. 1991. "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." Italy.
@misc{etde_10104081,
title = {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}
author = {Pescarini, M}
abstractNote = {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.}
place = {Italy}
year = {1991}
month = {Dec}
}