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Analysis of fuel relocation for the NRC/PNL Halden assemblies IFA-431, IFA-432, and IFA-513

Description: The effects of the thermally-induced cracking and subsequent relocation of UO/sub 2/ fuel pellets on the thermal and mechanical behavior of light-water reactor fuel rods during irradiation are quantified in this report. Data from the Nuclear Regulatory Commission/Pacific Northwest Laboratory Halden experiments on instrumented fuel assemblies (IFA) IFA-431, IFA-432, and IFA-513 are analyzed. Beginning-of-life in-reactor measurements of fuel center temperatures, linear heat ratings, and cladding … more
Date: April 1, 1980
Creator: Williford, R. E.; Mohr, C. L.; Lanning, D. D.; Cunningham, M. E.; Rausch, W. N. & Bradley, E. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Method for determining the uncertainty of gap conductance deduced from measured fuel centerline temperatures. [BWR]

Description: The paper describes the method which was developed to determine the uncertainties of gap conductances deduced from measured fuel centerline temperatures of NRC-RSR/BPNL fuel rods irradiated in the Halden Boiling Water Reactor. The ..integral..k(t)dt method is used to calculate the fuel surface temperature from the measured fuel centerline temperature and the fuel thermal conductivity. The gap conductance is calculated from the fuel surface temperature, the calculated cladding inside surface tem… more
Date: February 1, 1977
Creator: Hann, C. R.; Lanning, D. D.; Marshall, R. K.; Olsen, A. R. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of the in-pile pressure data from instrumented fuel assemblies IFA-431 and IFA-432.

Description: This report includes results of the examination of the in-pile pressure data from instrumented test assemblies IFA-431 and 432. The pressure data have been used to estimate the fission gas release fraction as a function of fuel burnup. Included are comparisons of the estimated release functions and those predicted by three fission gas release models using the experimental temperature histories of the fuel rods. These comparisons show that fuel temperature is the primary factor in determining fi… more
Date: October 1, 1979
Creator: Bradley, E. R.; Cunningham, M. E.; Lanning, D. D. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on the application of chaos theory to an alumina sensor for aluminum reduction cells

Description: Four chaos-related digital signal analysis (DSA) methods were applied to the analysis of voltage and current signals collected from aluminum electrolysis cells. Two separate data bases were analyzed: bench-scale laboratory experiments and a pilot-scale test. The objective was to assess the feasibility of using these types of data and analysis methods as the basis for a non-intrusive sensor to measure the alumina content in the electrolysis bath. This was the first time chaos theory approaches h… more
Date: March 1, 1992
Creator: Williford, R. E. & Windisch, C. F. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final report on the PNL program to develop an alumina sensor

Description: An alumina concentration sensor was required to ensure safe operating conditions for cermet inert anodes that were under development at the Pacific Northwest Laboratory (PNL)(a) for the electrolytic production of aluminum metal. The Sensors Development Program at PNL was conducted in response to this need for an alumina sensor. In all, eight different approaches to developing an alumina sensor were evaluated as part of this program. Each approach sought to correlate alumina concentration either… more
Date: October 1, 1992
Creator: Windisch, C. F. Jr.; Brenden, B. B.; Koski, O. H. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Data report for the NRC/PNL Halden assembly IFA-431.

Description: The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-431 as a part of the program entitled ''Experimental Verification of Steady State Fuel Codes,'' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure re… more
Date: April 1, 1978
Creator: Hann, C. R.; Bradley, E. R.; Cunningham, M. E.; Lanning, D. D.; Marshall, R. K. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data report for the NRC/PNL Halden Assembly IFA-432.

Description: The report presents the in-reactor data collected from the NRC/PNL Halden Assembly IFA-432 as a part of the program entitled ''Experimental Vertification of Steady State Fuel Codes,'' sponsored by the Fuel Behavior Research Branch of the USNRC. The purpose of this program is to reduce the uncertainties of calculating the thermal stored energy in an operating nuclear fuel rod. The report presents fuel centerline thermocouple readings, cladding elongation monitor readings, rod internal pressure r… more
Date: August 1, 1978
Creator: Hann, C. R.; Bradley, E. R.; Cunningham, M. E.; Lanning, D. D.; Marshall, R. K. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Manifestations of nonlinearity in fuel center thermocouple steady-state and transient data: implications for data analysis

Description: The interpretation and verification of fuel centerline thermocouple data are analyzed. Two new concepts are discussed along with their application to in-reactor data from IFA-432, a heavily instrumented six-rod Halden reactor test assembly sponsored by the Nuclear Regulatory Commission. The main ideas presented in this report are that: it is more useful to plot resistance versus power than simply to plot temperature versus power; and the response of the centerline temperature to a linear power … more
Date: January 1, 1979
Creator: Lanning, D. D.; Barnes, B. O. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermal-mechanical properties of cracked UO/sub 2/ pellets

Description: A series of experiments (IFA-431, 432, 513, and 527) sponsored by the Fuel Behavior Research Branch of the USNRC are being irradiated in the Halden Boiling Water Reactor to better define LWR fuel behavior over the normal operating range of power reactor fuel rods. One fuel behavior variable of interest is the thermally induced cracking of UO/sub 2/ fuel pellets. The effects of pellet cracking on the effective thermal conductivity and elastic moduli for the fragmented fuel were found to be prima… more
Date: November 1, 1980
Creator: Williford, R. E.; Mohr, C. L. & Lanning, D. D.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Final report on the application of chaos theory to an alumina sensor for aluminum reduction cells. Inert Electrodes Program

Description: Four chaos-related digital signal analysis (DSA) methods were applied to the analysis of voltage and current signals collected from aluminum electrolysis cells. Two separate data bases were analyzed: bench-scale laboratory experiments and a pilot-scale test. The objective was to assess the feasibility of using these types of data and analysis methods as the basis for a non-intrusive sensor to measure the alumina content in the electrolysis bath. This was the first time chaos theory approaches h… more
Date: March 1, 1992
Creator: Williford, R. E. & Windisch, C. F. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Effects of Pd, Rh, and Ru concentration on HCOOH decomposition during the processing of NCAW waste simulant

Description: The noble metals Pd, Rh, and Ru that are present in the Hanford high-level waste will be processed into a melter feed for vitrification and permanent disposal. The treatment of waste slurry with HCOOH, a step in producing a melter feed, results in the production of H{sub 2} and NH{sub 3} due to the catalytic activity of the noble metals. The presence of H{sub 2} and NH{sub 3} could lead to hazardous conditions in a treatment facility. This study determined the relationship between noble metals … more
Date: April 1, 1994
Creator: Patello, G. K.; Smith, H. D.; Wiemers, K. D.; Williford, R. E.; Bell, R. D. & Larson, D. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Alternate processing flowsheets for treating NCAW waste slurry with formic acid

Description: High-level waste stored at the US Department of Energy`s Hanford Site will be pretreated and fed to the Hanford Waste Virtrification Plant (HWVP). The reference flowsheet used to develop the pretreatment process calls for formic acid. However, the potential for generating H{sub 2} and NH{sub 3} during treatment of high-level waste (HLW) with HCOOH was identified at Pacific Northwest Laboratory by Wiemers. Work performed at PNL during FY 1991, FY 1992, and FY 1993 further documented the generati… more
Date: April 1, 1994
Creator: Smith, H. D.; Merz, M. D.; Wiemers, K. D.; Bell, R. D.; Williford, R. E. & Larson, D. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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High Burnup Effects Program A State-of-the-Technology Assessment

Description: Various analytical models and empirical correlations describing the fission gas release phenomenon were examined. An evaluation was made of the current pertinent experimental data on the subject of high burnup fission gas release. Data reported by individual investigators were compared and evaluated in relation to their applicability to the content and scope of the High Burnup Effects Program. These evaluations then form the bases for defining the data needs, and the selection of variables to b… more
Date: June 1, 1982
Creator: Rising, K. H.; Bradley, E. R.; Williford, R. E. & Freshley, M D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Precharacterization Report for Instrumented Fuel Assembly (IFA)-527

Description: This report is a resource document covering the rationale, design, fabrication, and preirradiation characterization of instrumented fuel assembly (IFA)-527. This assembly is being irradiated in the Halden Boiling Water Reactor (HBWR) in Norway as part of the Experimental Support and Development of Single-Rod Fuel Codes Program conducted by Pacific Northwest laboratory (PNL) and sponsored by the Fuel Behavior Research Branch of the U.S. Nuclear Regulatory Commission (NRC). Data from this assembl… more
Date: July 1, 1981
Creator: Cunningham, M. E.; Bradley, E. R.; Daniel, J. L.; Davis, N. C.; Lanning, D. D. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data Report for the Instrumented Fuel Assembly IFA-513

Description: This report presents the in-reactor data collected to date from the NRC/PNL Halden test assembly IFA-513. The irradiation test is part of an experimental program entitled 11 Experimental Support and Development of Single Rod Fuel Codes 11 sponsored by the Fuel Behavior Branch of the U.S. Nuclear Regulatory Commission (NRC). The purpose of this program is to reduce the uncertainties of predicting the thermal and mechanical behavior of an operating nuclear fuel rod. Fuel centerline temperatures, … more
Date: August 1, 1981
Creator: Bradley, E. R.; Cunningham, M. E.; Lanning, D. D. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Data Report for the NRC/PNL Halden Assembly IFA-432: April 1978-May 1980

Description: This report presents the in-reactor data collected from the U.S. Nuclear Regulatory Commission (NRC)/Pacific Northwest Laboratory (PNL) Halden test assembly IFA-432 for the period from April 1978 through May 1980. The irradiation test is part of an experimental program entitled 11 Experimental Support and Development of Single-Rod Fuel Codes" sponsored by the Fuel Behavior Research Branch of the NRC. The purpose of this program is to reduce the uncertainties of predicting the thermal and m… more
Date: April 1, 1981
Creator: Bradley, E. R.; Cunningham, M. E.; Lanning, D. D. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Cermet fuels for space power systems

Description: A refractory-metal matrix, UN-fueled cermet is a very promising fuel candidate for a wide range of multi-megawatt space reactor systems, e.g., steady-state, flexible duty-cycle, or bimodal, single- or two-phase liquid-metal cooled reactors, or thermionic reactors (Coomes et al. 1986, Takkuhen 1969, Unpublished ANL). Cermet fuel is especially promising for reactor designs that require operational strategies which incorporate rapid power changes because of its anticipated capability to withstand … more
Date: November 1, 1985
Creator: Barner, J. O.; Coomes, E. P.; Williford, R. E. & Neimark, L. A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Software requirements specification document for the AREST code development

Description: The Analysis of the Repository Source Term (AREST) computer code was selected in 1992 by the U.S. Department of Energy. The AREST code will be used to analyze the performance of an underground high level nuclear waste repository. The AREST code is being modified by the Pacific Northwest Laboratory (PNL) in order to evaluate the engineered barrier and waste package designs, model regulatory compliance, analyze sensitivities, and support total systems performance assessment modeling. The current … more
Date: November 1, 1993
Creator: Engel, D. W.; McGrail, B. P.; Whitney, P. D.; Gray, W. J.; Williford, R. E.; White, M. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Ion-Beam-Induced Defects and Defect Interactions in Perovskite-Structure Titanates

Description: Ion-beam irradiation of perovskite structures results in the production and accumulation of defects. Below a critical temperature, irradiation also leads to a crystalline-to-amorphous transformation. The critical temperature for amorphization under 800 keV Kr{sup +} ion irradiation is 425,440 and 550 K for SrTiO{sub 3}, CaTiO{sub 3} and BaTiO{sub 3}, respectively. The results of ion-channeling studies on SrTiO{sub 3} irradiated with 1.0 MeV Au{sup 2+} ions suggest that the crystalline-to-amorph… more
Date: August 23, 1999
Creator: Boatner, L. A.; Jiang, W.; Meldrum, A.; Thevuthasan, S.; Weber, W. J. & Williford, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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FRAPCON-2: A Computer Code for the Calculation of Steady State Thermal-Mechanical Behavior of Oxide Fuel Rods

Description: FRAPCON-2 is a FORTRAN IV computer code that calculates the steady state response of light Mater reactor fuel rods during long-term burnup. The code calculates the temperature, pressure, deformation, and tai lure histories of a fuel rod as functions of time-dependent fuel rod power and coolant boundary conditions. The phenomena modeled by the code include (a) heat conduction through the fuel and cladding, (b) cladding elastic and plastic deformation, (c) fuel-cladding mechanical interaction, (d… more
Date: January 1, 1981
Creator: Berna, G. A.; Bohn, M. P.; Rausch, W. N.; Williford, R. E. & Lanning, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Status of the USNRC/PNL Halden test IFA-432. [PWR; BWR]

Description: The NRC/PNL fuel assembly IFA-432 began irradiation in December 1975 and as of January 1980 had reached an assembly average burnup of 2120 GJ/kgU (24.5 GWd/MTM). The rods in this assembly are heavily instrumented and this has allowed a fairly thorough analysis of fuel behavior. The emphasis of the analysis has been to evaluate the observed changes in thermal/mechanical behavior. These changes are related to estimates of fuel density changes, fission gas release, and fuel cracking and relocation… more
Date: January 1, 1980
Creator: Bradley, E. R.; Cunningham, M. E.; Lanning, D. D. & Williford, R. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Experimental Verification of a Cracked Fuel Mechanical Model

Description: This report describes the results of a series of laboratory experiments conducted to independently verify a model that describes the nonlinear mechanical behavior of cracked fuel in pelletized UO{sub 2}/Zircaloy nuclear fuel rods under normal operating conditions. After a brief description of the analytical model, each experiment is discussed in detail. Experiments were conducted to verify the general behavior and numerical values for the three primary independent modelling parameters (effectiv… more
Date: December 1, 1982
Creator: Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Final report on the PNL program to develop an alumina sensor. Sensors Development Program

Description: An alumina concentration sensor was required to ensure safe operating conditions for cermet inert anodes that were under development at the Pacific Northwest Laboratory (PNL)(a) for the electrolytic production of aluminum metal. The Sensors Development Program at PNL was conducted in response to this need for an alumina sensor. In all, eight different approaches to developing an alumina sensor were evaluated as part of this program. Each approach sought to correlate alumina concentration either… more
Date: October 1, 1992
Creator: Windisch, C. F. Jr.; Brenden, B. B.; Koski, O. H. & Williford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of HWVP feed preparation chemistry for an NCAW simulant -- Fiscal year 1993: Effect of noble metals concentration on offgas generation and ammonia formation

Description: The High-Level Waste Vitrification Program is developing technology for the Department of Energy to immobilize high-level and transuranic wastes as glass for permanent disposal. Pacific Northwest Laboratory (PNL) is conducting laboratory-scale melter feed preparation studies using a HWVP simulated waste slurry, Neutralized Current Acid Waste (NCAW). A FY 1993 laboratory-scale study focused on the effects of noble metals (Pd, Rh, and Ru) on feed preparation offgas generation and NH{sub 3} produc… more
Date: March 1, 1995
Creator: Patello, G. K.; Wiemers, K. D.; Bell, R. D.; Smith, H. D.; Williford, R. E. & Clemmer, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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