High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961 (open access)

High Performance UO2 Program Quarterly Progress Report Number 2: July-September 1961

The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding if the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely fission gas release and central melting in fuel rods.
Date: October 1, 1961
Creator: Weidenbaum, B.
System: The UNT Digital Library
High Performance UO2 Program Fourth Quarterly Progress Report (open access)

High Performance UO2 Program Fourth Quarterly Progress Report

This phase of the program is concerned with irradiation of fuel assemblies to determine central temperature limitations.
Date: April 1, 1962
Creator: Weidenbaum, B.
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Fifth Quarterly Progress Report, January - March 1964 (open access)

Transition Boiling Heat Transfer Program; Fifth Quarterly Progress Report, January - March 1964

Summary: Tests with the two-rod assembly were performed with liquid film trippers attached to the unheated wall, and a variation in rod spacing. Experimental data and improved high-speed motion pictures have been obtained of transition boiling behavior. The changes of the local heat transfer process between nucleate and film boiling can be readily distinguished i the motion pictures. Observational test performed with very short fins on the heated surface resulted in essentially eliminating transition boiling temperature fluctuations and doubling the film boiling coefficient. These gains were attained without reduction of the critical heat flux
Date: April 1, 1964
Creator: Quinn, E. P.
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Fourth Quarterly Progress Report, October - December 1963 (open access)

Transition Boiling Heat Transfer Program; Fourth Quarterly Progress Report, October - December 1963

Summary: Heat transfer tests employing the two-rod test section without film tripping devices have been completed. Representations defining critical heat flux, transition boiling and film boiling behavior at high pressures and over a steam quality range of 25 to 90 percent are shown. Fabrication of a new observational test section was completed and initial test results with high-speed motion pictures were obtained. A test loop instability which was found to affect transition boiling behavior was detected and partially eliminated.
Date: January 1, 1964
Creator: Quinn, E. P.
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964 (open access)

Transition Boiling Heat Transfer Program; Sixth Quarterly Progress Report, April - June 1964

Summary: Transition boiling data was taken with an improved flow loop, to explore the influence of loop characteristics on rod temperature fluctuations the transition region was found to be much smaller than for comparable conditions with a different loop. Also the amplitude, and frequency of the temperature oscillations, were significantly less than before. These results indicate that loop characteristic and flow disturbance parameters play a prominent part in governing the transition temperature fluctuations. Additional two-rod transition boiling data are presented. The results include data taken at high wall temperature levels during a demonstration test at low steam qualities, and the effect of a change in rod spacing on heat transfer performance.
Date: July 1, 1964
Creator: Quinn, E. P.
System: The UNT Digital Library
Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964 (open access)

Two-Phase Pressure Losses Quarterly Progress Report: Eighth Quarter, November 12, 1963 - February 11, 1964

Technical report describing that voids were measured in a ½-inch by 1-3/4-inch channel with the S-1 insert (B(0)/B(1) = 0.4, L(0) = 0.1 inch), at 2 inches ahead of the insert (position A), ½-inch past the insert (position B), 5 inches past (position C), and 12 inches past (position D). The conditions were: P – 1000 psia, G = 1.00 x 10(6) lb/h-ft(2), and x = 18.8 percent. Average void and void distribution at position A are the same as for flow in a straight channel. Void distribution at position B shows that the stagnation region downstream of the inserts contains a high fraction of voids. Average void and void distribution at positions C and d show that the two-phase mixture becomes strongly mixed (homogenized) as a result of passing through he contraction-expansion inserts. Distribution at position D approaches the distribution at position A; i.e., the straight channel distribution.
Date: March 1, 1964
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
System: The UNT Digital Library
High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964 (open access)

High Power Density Development Project: Sixteenth Quarterly Progress Report, January-March 1964

Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC. Five tasks are in progress: (1) Task 1A-High Power Density Fuel Development, (2) Task 1B-Fuel Fabrication Development. Assembly, (3) Task II-Stability, Heat Transfer and Fluid Flow, (4) Task III-Physics Development, and (5) Task IV-Co-Ordination and Test Planning.
Date: April 1, 1964
Creator: Holladay, R. L.
System: The UNT Digital Library
High Power Density Development Project Fourth Quarterly Progress Report : January - March 1961 (open access)

High Power Density Development Project Fourth Quarterly Progress Report : January - March 1961

The fourth quarter of effort applied to the Consumers R & D Program is summarized in the following: high power density fuel development, fuel fabrication development, stability, heat transfer and fluid flow, physics development, operation planning and test coordination.
Date: April 1, 1961
Creator: Holland, L. K.
System: The UNT Digital Library
High Performance UO2 Program First Quarterly Progress Report: April-June 1961 (open access)

High Performance UO2 Program First Quarterly Progress Report: April-June 1961

A better understanding of the maximum operating characteristics that can be achieved with the use of UO2 as a reactor fuel is the primary purpose of this program for Euratom and the Atomic Energy Commission. During this program work will be undertaken in two areas that have been of concern to the reactor core designer for a long time, viz. fission gas release and central melting in fuel rods.
Date: July 1, 1961
Creator: Weidenbaum, B
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963) (open access)

Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: December 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964) (open access)

Accurate Nuclear Fuel Burnup Analyses; Ninth Quarterly Progress Report, (December 1963 - February 1964)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: March 1, 1964
Creator: Rider, B. F.; Peterson, J. P., Jr.; Ruiz, C. P. & Smith, F. R.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963 (open access)

Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963

Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date: September 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Luke, P. S., Jr. & Smith, F. R.
System: The UNT Digital Library
Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963 (open access)

Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows no size effect in the range of pipe sizes from 3/4 inch to 1-1/4 inch. The values lie below the Martinelli curve at the lower qualities (x<0.6), but at high qualities tend to be above the Martinelli curve. The single-phase loss coefficient for the three contraction-expansion inserts show very little Reynolds number effect in the range of channel Reynolds numbers from 3 x 10(4) to 5 x 10(5). The two-phase data for insert number 1 has not yet been reduced. The two-phase loss for insert numbers 2 and 3 lies generally below the loss prediction based on a homogeneous flow model. The two-phase loss for insert number 2 shows excellent agreement with the corresponding loss for the S-1 insert in …
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
System: The UNT Digital Library
Specific Zirconium Alloy Design Program Quarterly Progress Report: Sixth Quarter, July - September, 1963 (open access)

Specific Zirconium Alloy Design Program Quarterly Progress Report: Sixth Quarter, July - September, 1963

Summary: Fundamental studies in support of the alloy design work are complete except for the experimental determination of the diffusion of oxygen in alloy-doped non-stoichiometric ZrO2. Over 100 oxidation runs have now been made on samples of ZrO2 doped with 1 mole percent of the oxides of Al, Y, Fe, Cr, and Ni. The first round testing of 31 alloys is now essentially complete. Analysis of the steam corrosion rate and hydriding raw data taken at 300, 400, and 500 degrees C indicates that Zr-Cr and Zr-Cu-Fe alloys show the most promise for development for service in steam over the entire temperature range 300-500 degrees C. Maximum resistance to corrosion hydrogen embrittlement requires high initial ductility and thus low, perhaps less than ~2.5 a/o total alloy content. For any composition, susceptibility to hydrogen embrittlement depends on crystallographic texture of the component; under certain circumstances hydrogen embrittlement may be high anisotropic. The second-round testing of 10 selected Zr-Cr and Zr-Cu base alloys is now about 50% complete. Three alternate fabrication schedules were evaluated; and the preliminary results indicate that the Zr-Cu alloy tested is less sensitive to heat treatment than is the Zr-Cr alloy tested. Raising the final alpha annealing temperature …
Date: October 1, 1963
Creator: Klepfer, H. H.; Jaech, John L.; Douglass, D. L. (David Leslie), 1931-; Blood, R. E. & Perrine, H. E.
System: The UNT Digital Library
Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4 (open access)

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 4

The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
Date: October 1, 1963
Creator: Sorlie, T.
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; Third Quarterly Progress Report, July - September 1963 (open access)

Transition Boiling Heat Transfer Program; Third Quarterly Progress Report, July - September 1963

Summary: Initial critical heat flux, transition boiling temperature fluctuation, and film boiling coefficient data have been obtained on a two-rod cluster assembly at 1000 psia and 25 to 90 percent steam qualities. A representation showing the range of critical heat flux data is presented. Typical temperature recordings which indicate transition and film boiling behavior are shown. Fabrication of a new high pressure observational test section is nearly complete. An optical table and illumination system has been build and operationally tested for photographic use on the new observational section.
Date: October 1, 1963
Creator: Quinn, E. P.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; Second Quarterly Progress Report, (March - May 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: July 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library
Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2 (open access)

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 2

The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
Date: April 1, 1963
Creator: Quinn, E. P.
System: The UNT Digital Library
Two-Phase Pressure Losses Quarterly Progress Report: Fifth Quarter, February 12, 1963 - May 12, 1963 (open access)

Two-Phase Pressure Losses Quarterly Progress Report: Fifth Quarter, February 12, 1963 - May 12, 1963

Technical report describing that void measurements were made in the 1/2-inch by 1-3/4-inch rectangular channel, for both flow up and flow down, at pressures of 600, 1000, and 1400 psia, and at various flows and quantities. Results at 1000 psia and 20 percent quality show that for the lowest flow both the void distribution and the average void are much different for flow down than for flow up, the void fraction for flow down being much higher. However, when the flow is increased both the void distribution and average void for flow down tend to approach the corresponding values for flow up. At 1000 psia, both flow up and flow down, the void fraction for 5 percent quality increases gradually from the wall to the center of the channel, and peaks at the center. At 20 percent quality, the void fraction increases abruptly from the wall and tends to be constant over the middle 65 percent of the channel. the void fraction for flow down is always greater than for flow up, other things being equal.
Date: June 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Sixth Quarter, March 1963 - May 1963 (open access)

Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Sixth Quarter, March 1963 - May 1963

Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date: June 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr. & Luke, P. S., Jr.
System: The UNT Digital Library
Specific Zirconium Alloy Design Program Quarterly Progress Report: Fifth Quarter, April - June, 1963 (open access)

Specific Zirconium Alloy Design Program Quarterly Progress Report: Fifth Quarter, April - June, 1963

A program is in progress for the design of a zirconium base alloy for steam service as nuclear fuel cladding. Thirty-one alloys selected for study of corrosion rate, hydriding rate and hydrogen embrittlement are in test. The corrosion testing of 1800 coupons to 3000 hours at at 300, 400, and 500 degrees C in refreshed steam has been completed. Statistical data analysis of the corrosion results are reported and alloys showing better corrosion performance at all test temperatures than that for Zircaloy-1 are discussed. Preliminary data for hydrogen uptake after long exposures at 400 and 500 degrees C are presented; the uptake for alloys showing the best corrosion performance is discussed. Post-corrosion mechanical property measurements are also reported along with the preliminary results of x-ray diffraction and metallographic studies relating to hydrogen embrittlement. A wide variation in resistance to embrittlement at a given hydrogen level was observed and can be tentatively correlated with original ductility, crystallographic texture, and hydride platelet orientation. The testing of a second round of ten alloys is also in progress. Studies concerning the mechanism of corrosion and hydriding in zirconium alloy are also reported. The results of recent neutron activation analyses of stripped corrosion films are …
Date: July 1, 1963
Creator: Klepfer, H. H.; Jaech, John L.; Blood, R. E. & Douglass, D. L. (David Leslie), 1931-
System: The UNT Digital Library
Maritime Loop Irradiation Program, S-I-5-B-M Fuel Irradiation Water Chemistry, Final Report (open access)

Maritime Loop Irradiation Program, S-I-5-B-M Fuel Irradiation Water Chemistry, Final Report

Introduction: The purpose of this technical report is to review the water chemistry methods and equipment developed for use with the Maritime Loop Irradiation Program conducted in the General Electric Test Reactor (GETR) from December 2, 1960 to July 19, 1962. Special emphasis is given to areas having general application to other high purity water systems. The Appendix includes a discussion of specific conductivity and pH in high purity water systems. A major section of this report is devoted to a review of gross activity levels on coupons of two different surface finishes exposed in the loop coolant system for various time intervals. A major objective of the chemistry program was to select or develop analytical methods such that the analyses could be performed at the loop location by technical personnel who normally operate the loop. By this means, frequent samples were obtained and analyzed directly thus providing close monitoring and control of the loop water chemistry at minimum expense.
Date: August 1, 1963
Creator: Danielson, D. W.; Gilbert, R. S. & Panter, G. E.
System: The UNT Digital Library
Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 3 (open access)

Development Program for Increased Output in the Garigliano Nuclear Reactor. Quarterly Report No. 3

The United States and the European Atomic Energy Community (Euratom), on May 29, and June 18, 1958, signed an agreement which provides a basis for co-operation in programs for the advancement of the peaceful applications of atomic energy. The work described in this report represents the Joint U.S.-Euratom effort. The over-all development program is designed to obtain the test data and operating experience necessary to eventually realize a 50 percent increase in the output of the Garigliano Nuclear Power Station located at Sessa Aurunca (Campania, Italy). Two tasks are in progress: Task III-F involves the preparation of test specimens of reactor vessel material for irradiation; Task IV consists of the formulation of specification for a complete data logging and computer system.
Date: July 1, 1963
Creator: Sorlie, T.
System: The UNT Digital Library