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Title: Analysis of detailed neutron fluxes in a PWR pressure vessel by two- and three-dimensional PALLAS transport codes

Abstract

To examine the effect of modeling of a pressurized water reactor (PWR) on predicting neutron field at the beltline of its pressure vessel (PV), neutron transport calculations were performed for various models of a 1000-MW(electric) class PWR in three different geometries-(R,theta), (R,Z), and a combination of (X,Y,Z) and (R,theta). A three-dimensional calculation with PALLAS-XYZ is used as a standard for the other two-dimensional (R,theta) and (R,Z) calculations made with PALLAS-2DRT and -2DCY. The source normalization essential for the (R,theta) calculation is reasonably made by dividing the total source neutrons by an effective core length, which provides calculated results in fair agreement with those calculated with a standard model for both radial attenuation and azimuthal variation of the integral fluxes above 1.0 and 0.1 MeV and also of displacements per atom (dpa). The (R,Z) calculations made in two different models were reviewed to find which model is more reasonable in evaluating neutron integral fluxes and dpa in a pressure vessel without underestimation. The effect of neglect of the axial leakage in (R,theta) transport calculations on neutron fluxes in a PV at the beltline region indicates little effect up to the distance before the vessel outer surface in contrast with an appreciablemore » effect outside it.« less

Authors:
;
Publication Date:
Research Org.:
Ship Research Institute, Tokai Branch, Tokai-mura, Ibaraki-ken
OSTI Identifier:
5315664
Resource Type:
Journal Article
Journal Name:
Nucl. Technol.; (United States)
Additional Journal Information:
Journal Volume: 62:2
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; PRESSURE VESSELS; NEUTRON FLUX; PWR TYPE REACTORS; THREE-DIMENSIONAL CALCULATIONS; CALCULATION METHODS; COMPUTER CODES; NEUTRON FLUENCE; NEUTRON LEAKAGE; NEUTRON MONITORS; NEUTRON SPECTRA; NEUTRON TRANSPORT; TWO-DIMENSIONAL CALCULATIONS; CONTAINERS; MEASURING INSTRUMENTS; MONITORS; NEUTRAL-PARTICLE TRANSPORT; RADIATION FLUX; RADIATION MONITORS; RADIATION TRANSPORT; REACTORS; SPECTRA; WATER COOLED REACTORS; WATER MODERATED REACTORS; 210200* - Power Reactors, Nonbreeding, Light-Water Moderated, Nonboiling Water Cooled

Citation Formats

Kiyoshi, T, and Nobuo, S. Analysis of detailed neutron fluxes in a PWR pressure vessel by two- and three-dimensional PALLAS transport codes. United States: N. p., 1983. Web.
Kiyoshi, T, & Nobuo, S. Analysis of detailed neutron fluxes in a PWR pressure vessel by two- and three-dimensional PALLAS transport codes. United States.
Kiyoshi, T, and Nobuo, S. 1983. "Analysis of detailed neutron fluxes in a PWR pressure vessel by two- and three-dimensional PALLAS transport codes". United States.
@article{osti_5315664,
title = {Analysis of detailed neutron fluxes in a PWR pressure vessel by two- and three-dimensional PALLAS transport codes},
author = {Kiyoshi, T and Nobuo, S},
abstractNote = {To examine the effect of modeling of a pressurized water reactor (PWR) on predicting neutron field at the beltline of its pressure vessel (PV), neutron transport calculations were performed for various models of a 1000-MW(electric) class PWR in three different geometries-(R,theta), (R,Z), and a combination of (X,Y,Z) and (R,theta). A three-dimensional calculation with PALLAS-XYZ is used as a standard for the other two-dimensional (R,theta) and (R,Z) calculations made with PALLAS-2DRT and -2DCY. The source normalization essential for the (R,theta) calculation is reasonably made by dividing the total source neutrons by an effective core length, which provides calculated results in fair agreement with those calculated with a standard model for both radial attenuation and azimuthal variation of the integral fluxes above 1.0 and 0.1 MeV and also of displacements per atom (dpa). The (R,Z) calculations made in two different models were reviewed to find which model is more reasonable in evaluating neutron integral fluxes and dpa in a pressure vessel without underestimation. The effect of neglect of the axial leakage in (R,theta) transport calculations on neutron fluxes in a PV at the beltline region indicates little effect up to the distance before the vessel outer surface in contrast with an appreciable effect outside it.},
doi = {},
url = {https://www.osti.gov/biblio/5315664}, journal = {Nucl. Technol.; (United States)},
number = ,
volume = 62:2,
place = {United States},
year = {Mon Aug 01 00:00:00 EDT 1983},
month = {Mon Aug 01 00:00:00 EDT 1983}
}