contributor author | Wang, Xiaolin | |
contributor author | Shi, Youqing | |
contributor author | Bickel, Grant | |
contributor author | Robert, DeAbreu | |
date accessioned | 2023-11-29T19:35:32Z | |
date available | 2023-11-29T19:35:32Z | |
date copyright | 2/8/2023 12:00:00 AM | |
date issued | 2/8/2023 12:00:00 AM | |
date issued | 2023-02-08 | |
identifier issn | 2332-8983 | |
identifier other | ners_009_03_034501.pdf | |
identifier uri | http://yetl.yabesh.ir/yetl1/handle/yetl/4294881 | |
description abstract | The isotope ratio method (IRM) is a technique used for estimating the energy production in a fission reactor by measuring isotope ratios in nonfuel reactor components. This method has been successfully demonstrated on the estimation of cumulative energy production as well as plutonium production in graphite-moderated and light-water-moderated reactors for nonproliferation purposes. In this paper, IRM was used to estimate neutron fluence in Zr-2.5Nb materials irradiated in fast neutron (FN) irradiation facilities in the National Research Universal (NRU) reactor. Neutron fluence has been shown to be an important parameter for studying irradiation effects on the performance and properties of critical reactor components. Selected isotope ratios of hafnium and iron were used as indicators of the neutron fluence in Zr-2.5Nb sample materials. Correlations between neutron fluence and the indicator element isotope ratios were generated using the reactor physics simulation codes Winfrith improved multigroup scheme (WIMS)-AECL and SCALE/Oak Ridge Isotope GENeration code (ORIGEN). Inductively coupled plasma-mass spectrometry (ICP-MS) was used to obtain accurate measurements of the isotope ratios. Neutron fluence values estimated using IRM, were in good agreement with the values based on measured irradiation power histories of the NRU reactor. This study proposes a potential application of IRM to the estimation of neutron fluence for critical reactor components in heavy-water-moderated reactors such as pressure and calandria tubes in CANDU® reactors. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Estimate of Neutron Fluence Using Isotope Ratio Method for ZR-2.5NB Materials Irradiated in the National Research Universal Reactor | |
type | Journal Paper | |
journal volume | 9 | |
journal issue | 3 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4055931 | |
journal fristpage | 34501-1 | |
journal lastpage | 34501-5 | |
page | 5 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2023:;volume( 009 ):;issue: 003 | |
contenttype | Fulltext | |