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Geophysical and Geologic Field Measurements for the U16a.04 Tunnel, Nevada Test Site, Nevada with a Discussion of Geophysical Measurements in Horizontal Holes

Description: This report summarizes the results of the U.S. Geological Survey geophysical and geological studies of the rock in the U16a.04 tunnel in the Nevada Test Site.
Date: December 19, 1967
Creator: Carroll, Roger D.; Ege, John R.; Cunningham, M. J.; Muller, D. C. & Way, R. J.
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
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Two-dimensional computer simulation of hypervelocity impact cratering: some preliminary results for Meteor Crater, Arizona

Description: A computational approach used for subsurface explosion cratering has been extended to hypervelocity impact cratering. Meteor (Barringer) Crater, Arizona, was selected for our first computer simulation because it was the most thoroughly studied. It is also an excellent example of a simple, bowl-shaped crater and is one of the youngest terrestrial impact craters. Shoemaker estimates that the impact occurred about 20,000 to 30,000 years ago (Roddy (1977)). Initial conditions for this calculation i… more
Date: April 1, 1978
Creator: Bryan, J. B.; Burton, D. E.; Cunningham, M. E. & Lettis, L. A., Jr.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Two-Dimensional Computer Simulation of Hypervelocity Impact Cratering: Some Preliminary Results for Meteor Crater, Arizona

Description: A computational approach used for subsurface explosion cratering was extended to hypervelocity impact cratering. Meteor (Barringer) Crater, Arizona, was selected for the first computer simulation because it is one of the most thoroughly studied craters. It is also an excellent example of a simple, bowl-shaped crater and is one of the youngest terrestrial impact craters. Initial conditions for this calculation included a meteorite impact velocity of 15 km/s, meteorite mass of 1.67 x 10/sup 8/ kg… more
Date: June 1978
Creator: Bryan, J. B.; Burton, D. E.; Cunningham, M. E. & Lettis, L. A., Jr.
Item Type: Refine your search to only Article
Location: None
Partner: UNT Libraries Government Documents Department
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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
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Effects of fill gas composition and pellet eccentricity: comparison between instrumented fuel assemblies IFA-431 and IFA-432

Description: Two 6-rod, instrumented test assemblies, designated IFA-431 and IFA-432, were designed to study the effects of fabricated fuel - cladding gap size, fuel density and stability, fill gas composition, linear heat rate, and burnup. Rod 4 of each assembly was designed to study the effects of fuel - cladding geometry and minimum gas thermal conductivity upon heat transfer across the gap between the fuel and cladding. To accomplish this, mechanical restraint was used to form a concentric fuel - claddi… more
Date: April 1, 1979
Creator: Cunningham, M. E.; Williford, R. E. & Hann, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Startup data report for NRC/PNL Halden Assembly IFA-513

Description: This report presents data from the first month of operation of IFA-513, which is a heavily instrumented 6-rod test assembly in the Halden Reactor in Norway. The assembly is jointly sponsored by the Halden Project and the Nuclear Regulatory Commission (NRC), and is part of a series of irradiation tests sponsored by the NRC to verify its single-rod fuel modeling computer programs. All the rods in the series are of the basic BWR-6 design with variations in gap size, fuel type, fill gas composition… more
Date: July 1, 1979
Creator: Lanning, D. D. & Cunningham, M. 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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Post-irradiation data analysis for NRC/PNL Halden assembly IFA-431

Description: Results are presented for the post irradiation examination performed on IFA-431, which was a 6-rod test fuel assembly irradiated in Halden Reactor, Norway, under sponsorship of the Nuclear Regulatory Commission. The irradiation conditions included: peak powers of 33 kW/m; coolant pressure and temperature of 3.3 MPa and 240/sup 0/C, respectively; and peak burnup of 4300 MWd/MTM. IFA-431 included instrumented rods of basic boiling water reactor design, with variations in fill gas composition, gap… more
Date: October 1, 1979
Creator: Nealley, C.; Lanning, D. D.; Cunningham, M. E. & Hann, C. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Interpretation of fuel centerline thermocouple response to reactor scrams

Description: This report compares and contrasts fuel thermocouple scram responses from the low-burnup assemblies IFA-513 and IFA-505 and the high-burnup assembly IFA-432. Even on a qualitative basis it is observed that the IFA-432 thermocouple responses are sluggish relative to that of low-burnup counterparts in rods of equivalent thermal resistance and design/enrichment. By numerical analysis, it is concluded that this apparent sluggishness is due to thermocouple decalibration, and an estimate of the decal… more
Date: January 1, 1980
Creator: Lanning, D. D. & Cunningham, M. E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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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
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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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Application of Linear Propagation of Errors to Fuel Rod Temperature and Stored Energy Calculations

Description: Linear propagatlon of errors evaluates modeling uncertainty by approximating a function of interest by first-order Taylor's series expansions and then approximating the variance of the function by the variance of the linear approximation. This report discusses uncertainty analysis for different nuclear fuel rod designs, the process of model validation, and the effect of cracked pellet fuel models upon temperabre uncertainty. Using a postulated power history, the uncertainty for the predicted th… more
Date: October 1, 1980
Creator: Cunningham, M. E.; Olsen, A. R.; Lanning, D. D. & Willford, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Performance Annual Report for 1979

Description: This annual report, the second in a series, provides a brief description of fuel performance in commercial nuclear power plants. Brief summaries are given of fuel surveillance programs, fuel performance problems, and fuel design changes. References to additional, more detailed, information and related NRC evaluation are provided.
Date: January 1, 1981
Creator: Tokar, M.; Mailey, W. J. & Cunningham, M. 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-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
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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
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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
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Experiment Operations Plan for a Loss-of-Coolant Accident Simulation in the National Research Universal Reactor Materials Test 2

Description: A loss-of-coolant accident (LOCA) simulation program is evaluating the thermal-hydraulic and mechanical effects on pressurized water reactor (PWR) test fuel bundles. This Experiment Operation Plan (EOP) Addendum 2, together with the referenced EOP, describes the desired operating conditions and additional hazards review associated with the four-part MT-2 experiment. The primary portions of the experiment, MT-2.2 and MT-2.3, will evaluate the following: 1) the mechanical deformation of pressuriz… more
Date: September 1, 1981
Creator: Russcher, G. E.; Barner, J. O.; Hesson, G. M.; Wilson, C. L.; Parchen, L. J.; Cunningham, M. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Observation of Porosity Reduction in a Densification-Prone Test Fuel Rod: Data and Analysis

Description: Instrumented fuel assembly (IFA)-431 was irradiated in the Halden Boiling Water Reactor (HBWR) for the purpose of extending the steady-state data base. Rod 6 of this assembly began irradiation with UO{sub 2} fuel of 92% theoretical density (TD) that was unstable with respect to in-reactor densification. Thermal resintering tests resulted in a final density of 95.3% TD while post-irradiation examination (PIE) indicated a final density of 96.5% TD. Observed microstructural changes were consistent… more
Date: October 1, 1981
Creator: Cunningham, M. E.; Daniel, J. L. & Lanning, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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End-of-irradiation data report for the instrumented fuel assembly (IFA)-527. [PWR; BWR]

Description: This report presents data obtained during the irradiation of the six-rod instrumented fuel assembly (IFA)-527 in the Halden Boiling Water Reactor (HBWR), Halden, Norway. This assembly is the last in a series of US Nuclear Regulatory Commission (NRC)-sponsored tests to obtain data for the development and verification of steady-state fuel performance computer codes. IFA-527 contains five identical rods with high-density stable fuel pellets and 230-..mu..m diametral gaps and one rod with similar f… more
Date: May 1, 1982
Creator: Cunningham, M. E. & Lanning, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final data report for the instrumented fuel assembly (IFA)-432

Description: This report presents the in-reactor data collected during the irradiation of the six-rod instrumented fuel assembly (IFA)-432 in the Halden Boiling Water Reactor (HBWR) from June 1980 through June 1981. This Pacific Northwest Laboratory (PNL)-designed assembly was one of a series of US Nuclear Regulatory Commission (NRC)-sponsored tests to obtain data for the development and verification of steady-state fuel performance computer codes. IFA-432 operated from December 1975 until June 1981, when i… more
Date: June 1, 1982
Creator: Bradley, E. R.; Cunningham, M. E. & Lanning, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Control of degradation of spent LWR (light-water reactor) fuel during dry storage in an inert atmosphere

Description: Dry storage of Zircaloy-clad spent fuel in inert gas (referred to as inerted dry storage or IDS) is being developed as an alternative to water pool storage of spent fuel. The objectives of the activities described in this report are to identify potential Zircaloy degradation mechanisms and evaluate their applicability to cladding breach during IDS, develop models of the dominant Zircaloy degradation mechanisms, and recommend cladding temperature limits during IDS to control Zircaloy degradation… more
Date: October 1, 1987
Creator: Cunningham, M. E.; Simonen, E. P.; Allemann, R. T.; Levy, I. S. & Hazelton, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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