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Thermocouples For High Temperature In-Pile Testing

Description: Many advanced nuclear reactor designs require new fuel, cladding and structural materials. Data are needed to characeterize the performance of these new materials in high temperature, oxidizing and radiation conditions. To obtain this data, robust instrumentation is needed htat can survive proposed test conditions. Traditional methods for measuring temperature in-pile degrade at temperatures above 1080 degrees C. Hence, a project was intiated to develop specialized thermocouples for high temper… more
Date: November 1, 2005
Creator: Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

EVALUATION OF LVDTS FOR USE IN ATR IRRADIATION EXPERIMENTS

Description: New materials are being considered for fuel, cladding, and structures in next generation and existing nuclear reactors. Such materials can experience significant dimensional changes during high temperature irradiation. Currently, these changes are determined by repeatedly irradiating a specimen for a defined period of time in the Advanced Test Reactor (ATR) and then removing it from the reactor for evaluation. The time and labor to remove, examine, and return irradiated samples for each measure… more
Date: April 1, 2009
Creator: Knudson, D. L. & Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

Test Data for USEPR Severe Accident Code Validation

Description: This document identifies data that can be used for assessing various models embodied in severe accident analysis codes. Phenomena considered in this document, which were limited to those anticipated to be of interest in assessing severe accidents in the USEPR developed by AREVA, include: • Fuel Heatup and Melt Progression • Reactor Coolant System (RCS) Thermal Hydraulics • In-Vessel Molten Pool Formation and Heat Transfer • Fuel/Coolant Interactions during Relocation • Debris Heat Loads to the … more
Date: May 1, 2007
Creator: Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

In-Vessel Retention - Recent Efforts and Future Needs

Description: In-vessel retention (IVR) of core melt is a key severe accident management strategy adopted by some operating nuclear power plants and proposed for some advanced light water reactors (ALWRs). If there were inadequate cooling during a reactor accident, a significant amount of core material could become molten and relocate to the lower head of the reactor vessel, as happened in the Three Mile Island Unit 2 (TMI-2) accident. If it is possible to ensure that the vessel head remains intact so that r… more
Date: October 1, 2004
Creator: Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

Most likely failure location during severe accident conditions

Description: This paper describes preliminary results from which finite element calculation results are used in conjunction with analytical calculation results to predict failure in different LWR vessel designs during a severe accident. Detailed analyses are being performed to investigate the relative likelihood of a BWR vessel and drain line penetration to fail during a wide range of severe accident conditions. Analytically developed failure maps, which were developed in terms of dimensionless groups, are … more
Date: December 31, 1991
Creator: Rempe, J. L. & Allison, C. M.
Partner: UNT Libraries Government Documents Department
open access

Most Likely Failure Location During Severe Accident Conditions

Description: This paper describes preliminary results from which finite element calculation results are used in conjunction with analytical calculation results to predict failure in different LWR vessel designs during a severe accident. Detailed analyses are being performed to investigate the relative likelihood of a BWR vessel and drain line penetration to fail during a wide range of severe accident conditions. Analytically developed failure maps, which were developed in terms of dimensionless groups, are … more
Date: January 1, 1991
Creator: Rempe, J. L. & Allison, C. M.
Partner: UNT Libraries Government Documents Department
open access

Thermal Properties of Structural Materials Found in Light Water Reactor Vessels

Description: High temperature material property data for structural materials used in existing Light Water Reactors (LWRs) are limited. Often, extrapolated values recommended in the literature differ significantly. To reduce such uncertainties, new data for SA533 Grade B, Class 1 (SA533B1) low alloy steel, Stainless Steel 304 (SS304), and Inconel 600, found in Light Water Reactor (LWR) vessels and penetrations, were acquired and tested using material property systems available at the High Temperature Test L… more
Date: November 1, 2009
Creator: Daw, J. E.; Rempe, J. L. & Knudson, D. L.
Partner: UNT Libraries Government Documents Department
open access

High Temperature Thermocouples For In-pile Applications

Description: Traditional methods for measuring temperature in-pile degrade at temperatures above 1080 degrees C. Hence, a project has been initiated to explore the use of specialized thermocouples that are composed of materials that are able to withstand higher temperature, in-pile test conditions. Results from efforts to develop, fabricate and evaluate the performance of these specialized thermocouples are reported in this paper. Candidate materials were evaluated for their ability to withstand irradiation… more
Date: October 1, 2005
Creator: Rempe, J. L. & Wilkins, S. C.
Partner: UNT Libraries Government Documents Department
open access

Light water reactor lower head failure analysis

Description: This document presents the results from a US Nuclear Regulatory Commission-sponsored research program to investigate the mode and timing of vessel lower head failure. Major objectives of the analysis were to identify plausible failure mechanisms and to develop a method for determining which failure mode would occur first in different light water reactor designs and accident conditions. Failure mechanisms, such as tube ejection, tube rupture, global vessel failure, and localized vessel creep rup… more
Date: October 1, 1993
Creator: Rempe, J. L.; Chavez, S. A. & Thinnes, G. L.
Partner: UNT Libraries Government Documents Department
open access

PST user`s guide

Description: The Parametric Source Term (PST) software allows estimation of radioactivity release fractions for Level 2 Probabilistic Safety Assessments (PSAs). PST was developed at the Idaho National Engineering Laboratory (INEL) for the Nuclear Regulatory Commission`s (NRC`s) Accident Sequence Precursor (ASP) Program. PST contains a framework of equations that model activity transport between volumes in the release pathway from the core, through the vessel, through the containment, and to the environment.… more
Date: October 1, 1996
Creator: Rempe, J. L.; Cebull, M. J. & Gilbert, B. G.
Partner: UNT Libraries Government Documents Department
open access

Design report on SCDAP/RELAP5 model improvements - debris bed and molten pool behavior

Description: the SCDAP/RELAP5/MOD3 computer code is designed to describe the overall reactor coolant system thermal-hydraulic response, core damage progression, and in combination with VICTORIA, fission product release and transport during severe accidents. Improvements for existing debris bed and molten pool models in the SCDAP/RELAP5/MOD3.1 code are described in this report. Model improvements to address (a) debris bed formation, heating, and melting; (b) molten pool formation and growth; and (c) molten p… more
Date: November 1, 1994
Creator: Allison, C. M.; Rempe, J. L. & Chavez, S. A.
Partner: UNT Libraries Government Documents Department
open access

Status Report on Efforts to Enhance Instrumentation to Support Advanced Test Reactor Irradiations

Description: The Department of Energy (DOE) designated the Advanced Test Reactor (ATR) as a National Scientific User Facility (NSUF) in April 2007 to support U.S. leadership in nuclear science and technology. By attracting new research users - universities, laboratories, and industry - the ATR NSUF facilitates basic and applied nuclear research and development, further advancing the nation's energy security needs. A key component of the ATR NSUF effort is to prove new in-pile instrumentation techniques that… more
Date: March 1, 2011
Creator: Rempe, J. L.; Knudson, D. L. & Daw, J. E.
Partner: UNT Libraries Government Documents Department
open access

HIGH TEMPERATURE THERMAL AND STRUCTURAL MATERIAL PROPERTIES FOR METALS USED IN LWR VESSELS

Description: Because of the impact that melt relocation and vessel failure may have on subsequent progression and associated consequences of a Light Water Reactor (LWR) accident, it is important to accurately predict heating and relocation of materials within the reactor vessel, heat transfer to and from the reactor vessel, and the potential for failure of the vessel and structures within it. Accurate predictions of such phenomena require high temperature thermal and structural properties. However, a review… more
Date: June 1, 2008
Creator: Rempe, J. L.; Knudson, D. L.; Daw, J. E. & Crepeau, J. C.
Partner: UNT Libraries Government Documents Department
open access

HTIR-TC Compensating Extension Wire Evaluations

Description: In an effort to reduce production costs for the doped molybdenum/niobium alloy High Temperature Irradiation Resistant Thermocouples (HTIR-TCs) recently developed by the Idaho National Laboratory, a series of evaluations were completed to identify an optimum compensating extension cable. As documented in this report, results indicate that of those combinations tested, two inexpensive, commercially-available copper nickel alloy wires approximate the low temperature (0 to 500 °C) thermoelectric ou… more
Date: September 1, 2007
Creator: Daw, J. E.; Rempe, J. L.; Knudson, D. L.; Wilkins, S. C. & Crepeau, J. C.
Partner: UNT Libraries Government Documents Department
open access

USE OF SILICON CARBIDE MONITORS IN ATR IRRADIATION TESTING

Description: In April 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) a National Scientific User Facility (NSUF) to advance US leadership in nuclear science and technology. By attracting new users from universities, laboratories, and industry, the ATR will support basic and applied nuclear research and development and help address the nation's energy security needs. In support of this new program, the Idaho National Laboratory (INL) has developed in-house capabilities to fabr… more
Date: July 1, 2012
Creator: Davis, K. L.; Chase, B.; Unruh, T.; Knudson, D. & Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Specialized Thermocouples for High-Temperature In-Pile Testing

Description: Many advanced nuclear reactor designs require new fuel, cladding, and structural materials. Data are needed to characterize the performance of these new materials in high temperature, oxidizing, and radiation conditions. To obtain this data, robust instrumentation is needed that can survive proposed test conditions. Standard thermocuoples for measuring temperature in-pile degrade at temperatures above 1100 ºC. Hence, INL initiated a project to develop specialized thermocouples for high temperat… more
Date: June 1, 2006
Creator: Rempe, J. L.; Knudson, D. L.; Condie, K. G. & Wilkins, S. C.
Partner: UNT Libraries Government Documents Department
open access

MELT WIRE SENSORS AVAILABLE TO DETERMINE PEAK TEMPERATURES IN ATR IRRADIATION TESTING

Description: In April 2007, the Department of Energy (DOE) designated the Advanced Test Reactor (ATR) a National Scientific User Facility (NSUF) to advance US leadership in nuclear science and technology. By attracting new users from universities, laboratories, and industry, the ATR will support basic and applied nuclear research and development and help address the nation's energy security needs. In support of this new program, the Idaho National Laboratory (INL) has developed in-house capabilities to fabr… more
Date: July 1, 2012
Creator: Davis, K. L.; Knudson, D.; Daw, J.; Palmer, J. & Rempe, J. L.
Partner: UNT Libraries Government Documents Department
open access

Critical Heat Flux for Downward-Facing Boiling on a Coated Hemispherical Vessel Surrounded by an Insulation Structure

Description: An experimental study was performed to evaluate the effects of surface coating and an enhanced insulation structure on the downward facing boiling process and the critical heat flux on the outer surface of a hemispherical vessel. Steady-state boiling tests were conducted in the Subscale Boundary Layer Boiling (SBLB) facility using an enhanced vessel/insulation design for the cases with and without vessel coatings. Based on the boiling data, CHF correlations were obtained for both plain and coat… more
Date: May 1, 2005
Creator: Yang, J.; Cheung, F. B.; Rempe, J. L.; Suh, K. Y. & Kim, S. B.
Partner: UNT Libraries Government Documents Department
open access

Correlations of Nucleate Boiling Heat Transfer and Critical Heat Flux for External Reactor Vessel Cooling

Description: Four types of steady-state boiling experiments were conducted to investigate the efficacy of two distinctly different heat transfer enhancement methods for external reactor vessel cooling under severe accident conditions. One method involved the use of a thin vessel coating and the other involved the use of an enhanced insulation structure. By comparing the results obtained in the four types of experiments, the separate and integral effect of vessel coating and insulation structure were determi… more
Date: July 1, 2005
Creator: Yang, J.; Cheung, F. B.; Rempe, J. L.; Suh, K. Y. & Kim, S. B.
Partner: UNT Libraries Government Documents Department
open access

Viability of Pushrod Dilatometry Techniques for High Temperature In-Pile Measurements

Description: To evaluate the performance of new fuel, cladding, and structural materials for use in advanced and existing nuclear reactors, robust instrumentation is needed. Changes in material deformation are typically evaluated out-of-pile, where properties of materials are measured after samples were irradiated for a specified length of time. To address this problem, a series of tests were performed to examine the viability of using pushrod dilatometer techniques for in-pile instrumentation to measure de… more
Date: March 1, 2008
Creator: Daw, J. E.; Rempe, J. L.; Knudson, D. L.; Condie, K. G. & Crepeau, J. C.
Partner: UNT Libraries Government Documents Department
open access

Evaluations of University of Wisconsin Silicon Carbide Temperature Monitors 300 LO and 400 LO B

Description: Silicon carbide (SiC) temperature monitors 05R4-02-A KG1403 (300 LO) and 05R4-01-A KG1415 (400 LO B) were evaluated at the High Temperature Test Lab (HTTL) to determine their peak irradiation temperatures. HTTL measurements indicate that the peak irradiation temperature for the 300 LO monitor was 295 {+-} 20 C and the peak irradiation temperature for the 400 LO B monitor was 294 {+-} 25 C. Two silicon carbide (SiC) temperature monitors irradiated in the Advanced Test Reactor (ATR) were evaluate… more
Date: December 1, 2011
Creator: Davis, K. L.; Rempe, J. L.; Knudson, D. L.; Chase, B. M. & Unruh, T. C.
Partner: UNT Libraries Government Documents Department
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