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Title: SENSITIVITY EVALUATION OF THE DAILY THERMAL PREDICTIONS OF THE AGR-2 EXPERIMENT IN THE ADVANCED TEST REACTOR

Abstract

A temperature sensitivity evaluation has been performed for the AGR-2 fuel experiment on an individual capsule. A series of cases were compared to a base case by varying different input parameters into the ABAQUS finite element thermal model. These input parameters were varied by ±10% to show the temperature sensitivity to each parameter. The most sensitive parameters are the outer control gap distance, heat rate in the fuel compacts, and neon gas fraction. Thermal conductivity of the fuel compacts and thermal conductivity of the graphite holder were in the middle of the list for sensitivity. The smallest effects were for the emissivities of the stainless steel and graphite, along with gamma heat rate in the non-fueled components. Sensitivity calculations were also performed varying with fast neutron fluence, showing a general temperature rise with an increase in fast neutron fluence. This is a result of the control gas gap becoming larger due to the graphite holder shrinkage with neutron damage. A smaller sensitivity is due to the thermal conductivity of the fuel compacts and graphite holder decreasing with fast neutron fluence.

Authors:
ORCiD logo [1]; ORCiD logo [1]; ORCiD logo [1]
  1. Idaho National Laboratory
Publication Date:
Research Org.:
Idaho National Lab. (INL), Idaho Falls, ID (United States)
Sponsoring Org.:
USDOE Office of Nuclear Energy (NE)
OSTI Identifier:
1566069
Report Number(s):
INL/CON-15-34140-Rev000
DOE Contract Number:  
DE-AC07-05ID14517
Resource Type:
Conference
Resource Relation:
Conference: ASME Power & Energy 2015: Energy Solutions for a Sustainable Future, San Diego, California, 06/28/2015 - 07/02/2015
Country of Publication:
United States
Language:
English
Subject:
11 - NUCLEAR FUEL CYCLE AND FUEL MATERIALS; low enriched uranium oxycarbide (LEUCO); post-irradiation examination (PIE); tri-structural-isotropic (TRISO); advanced gas-cooled reactor (AGR); Advanced Test Reactor (ATR; Next Generation Nuclear Plant (NGNP); ABAQUS

Citation Formats

Hawkes, Grant, Sterbentz, Jim, and Pham, Binh. SENSITIVITY EVALUATION OF THE DAILY THERMAL PREDICTIONS OF THE AGR-2 EXPERIMENT IN THE ADVANCED TEST REACTOR. United States: N. p., 2015. Web. doi:10.1115/NUCLRF2015-49698.
Hawkes, Grant, Sterbentz, Jim, & Pham, Binh. SENSITIVITY EVALUATION OF THE DAILY THERMAL PREDICTIONS OF THE AGR-2 EXPERIMENT IN THE ADVANCED TEST REACTOR. United States. doi:10.1115/NUCLRF2015-49698.
Hawkes, Grant, Sterbentz, Jim, and Pham, Binh. Mon . "SENSITIVITY EVALUATION OF THE DAILY THERMAL PREDICTIONS OF THE AGR-2 EXPERIMENT IN THE ADVANCED TEST REACTOR". United States. doi:10.1115/NUCLRF2015-49698. https://www.osti.gov/servlets/purl/1566069.
@article{osti_1566069,
title = {SENSITIVITY EVALUATION OF THE DAILY THERMAL PREDICTIONS OF THE AGR-2 EXPERIMENT IN THE ADVANCED TEST REACTOR},
author = {Hawkes, Grant and Sterbentz, Jim and Pham, Binh},
abstractNote = {A temperature sensitivity evaluation has been performed for the AGR-2 fuel experiment on an individual capsule. A series of cases were compared to a base case by varying different input parameters into the ABAQUS finite element thermal model. These input parameters were varied by ±10% to show the temperature sensitivity to each parameter. The most sensitive parameters are the outer control gap distance, heat rate in the fuel compacts, and neon gas fraction. Thermal conductivity of the fuel compacts and thermal conductivity of the graphite holder were in the middle of the list for sensitivity. The smallest effects were for the emissivities of the stainless steel and graphite, along with gamma heat rate in the non-fueled components. Sensitivity calculations were also performed varying with fast neutron fluence, showing a general temperature rise with an increase in fast neutron fluence. This is a result of the control gas gap becoming larger due to the graphite holder shrinkage with neutron damage. A smaller sensitivity is due to the thermal conductivity of the fuel compacts and graphite holder decreasing with fast neutron fluence.},
doi = {10.1115/NUCLRF2015-49698},
journal = {},
number = ,
volume = ,
place = {United States},
year = {2015},
month = {6}
}

Conference:
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