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Title: Power distribution and control element reactivity changes in Advanced Test Reactor due to beryllium reflector redesign

Abstract

A redesigned beryllium reflector has been installed in the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory. The main feature of the redesigned reflector was the introduction of horizontal sawcuts at 13 different elevations immediately adjacent to the fuel region of the core. Two other significant core design changes were made at the same time: (1) the hafnium plates on the outer shim control cylinders were reduced in arc length from 134/sup 0/ to 122/sup 0/, and (2) the inside diameter of the center flux trap baffle was reduced from 85.725 mm (3.375 in.) to 82.2325 mm (3.2375 in.) to increase the metal-to-water ratio in the center flux trap baffle region. Following installation of the redesigned components, zero power physics tests were made with a core of new fuel elements prior to resuming full power operation. The power distribution measurements were obtained in both the ATR and ATRC by irradiating U--Al flux wires in each of the forty fuel elements. The irradiated wires are counted for beta activity which is then converted to specific fission rate. The specific fission rate data are used to calculate point power densities and fuel element powers.

Authors:
;
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
OSTI Identifier:
6142455
Report Number(s):
CONF-790807-1
TRN: 79-016958
DOE Contract Number:  
EY-76-C-07-1570
Resource Type:
Conference
Resource Relation:
Conference: Topical conference on reactor operating experience, Arlington, TX, USA, 5 Aug 1979
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; ATR REACTOR; CONTROL ROD WORTHS; NEUTRON REFLECTORS; REACTOR CORES; MODIFICATIONS; POWER DISTRIBUTION; REACTOR KINETICS; ENRICHED URANIUM REACTORS; IRRADIATION REACTORS; KINETICS; MATERIALS TESTING REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; TANK TYPE REACTORS; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS; 220600* - Nuclear Reactor Technology- Research, Test & Experimental Reactors

Citation Formats

Gregory, W D, and Zimmermann, W L. Power distribution and control element reactivity changes in Advanced Test Reactor due to beryllium reflector redesign. United States: N. p., 1979. Web.
Gregory, W D, & Zimmermann, W L. Power distribution and control element reactivity changes in Advanced Test Reactor due to beryllium reflector redesign. United States.
Gregory, W D, and Zimmermann, W L. Mon . "Power distribution and control element reactivity changes in Advanced Test Reactor due to beryllium reflector redesign". United States. https://www.osti.gov/servlets/purl/6142455.
@article{osti_6142455,
title = {Power distribution and control element reactivity changes in Advanced Test Reactor due to beryllium reflector redesign},
author = {Gregory, W D and Zimmermann, W L},
abstractNote = {A redesigned beryllium reflector has been installed in the Advanced Test Reactor (ATR) at the Idaho National Engineering Laboratory. The main feature of the redesigned reflector was the introduction of horizontal sawcuts at 13 different elevations immediately adjacent to the fuel region of the core. Two other significant core design changes were made at the same time: (1) the hafnium plates on the outer shim control cylinders were reduced in arc length from 134/sup 0/ to 122/sup 0/, and (2) the inside diameter of the center flux trap baffle was reduced from 85.725 mm (3.375 in.) to 82.2325 mm (3.2375 in.) to increase the metal-to-water ratio in the center flux trap baffle region. Following installation of the redesigned components, zero power physics tests were made with a core of new fuel elements prior to resuming full power operation. The power distribution measurements were obtained in both the ATR and ATRC by irradiating U--Al flux wires in each of the forty fuel elements. The irradiated wires are counted for beta activity which is then converted to specific fission rate. The specific fission rate data are used to calculate point power densities and fuel element powers.},
doi = {},
url = {https://www.osti.gov/biblio/6142455}, journal = {},
number = ,
volume = ,
place = {United States},
year = {1979},
month = {1}
}

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