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PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR JULY 1, 1959- SEPTEMBER 30, 1959

Description: ABS>Fuel Element Research and Development. Dynamic and static corrosion tests on 8001 Al were completed. Annealmmmg of 1100 cladding on 5083 and M400 cladding on X2219 were tested at 500 deg C, and investigation continued on producing X8101 Al alloy cladding in tube plates by extrusion. Boiler fuel element capsule irradiation tests and subassembly tests are described Heat transfer loop studies and fuel fabrication for the critical facility are reported. Boiler fuel element mechanical design and testing progress is desc ribed. and the superheater fuel element temperature evaluating routine is discussed. Low- enrichment superheater fuel element development included design studies and stainless steel powder and UO/sub 2/ powder fabrication studies Reactor Mechanical Studies. Research is reported on vessel and structure design, fabrication, and testing, recirculation system design, steam separator tests, and control rod studies. Nuclear Analysis. Reactor physics studies are reported on nuclear constants, baffle plate analysis, comparison of core representations, delayed neutron fraction. and shielding analysis of the reactor building. Reactor and system dynamics and critical experiments were also studied. Chemistry. Progress is reported on recombiner. radioactive gas removal and storage, ion exchanger and radiochemical processing. (For preceding period see ACNP-5915.) (T.R.H.)
Date: October 31, 1960
Partner: UNT Libraries Government Documents Department

CONTROL ROD DRIVE PROTO-TYPE TEST REPORT

Description: An evaluation under simulated Pathfinder reactor operating conditions of a prototype Pathfinder control rod drive (described) indicated that the unit will perform satisfactorily under all Pathfinder operating conditions. Tests were performed on individual components of the drive and on the assembled drive. (D.C.W.)
Date: October 25, 1963
Creator: Patterson, J.; Duewel, E.; Kern, R.; Jury, M.; Grenda, R.; McIlheran, A. et al.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT COOLANT DISTRIBUTION TESTS. Final Report

Description: Tests were made to determine the head loss coefficient through the inlet plenum of the Pathfinder reactor and to determine the now distribution among the fuel element nozzles for various operating conditions--with all three pumps operating at the same flow rate and with any combination of only two pumps operating at the same flow rate. A quarter-scale wooden model was used for the tests. Air was used as the fluld. The loss coefficient was determined to be 1.8 plus or minus 0.3. The velocities of flow through the fuel element nozzles were determined to be within plus or minus 5 per cent of average flow when all pumps are operating and within plus or minus 10 per cent of average flow when only two pumps are operating. (auth)
Date: November 15, 1959
Creator: Wilson, J. & Styles, R.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. END CLOSURE DEVELOPMENT FOR LOW ENRICHMENT SUPERHEATER FUEL RODS

Description: Research on a welding process for closing the ends of pathfinder fuel elements is reported. Optimum parameters for certain variables (amperage, weld travel, preheat, etc.) affecting weld quality were determined, and two modified end cap designs were investigated and found to reduce weld sensitivity to certain variables. Use of chills on the fuel tube greatly improved weld puddie geometry and microstructure. Optimum weld parameters for rods containing UO/sub 2/ fuel were experimentally established. (D.C.W.)
Date: July 30, 1963
Creator: Boschke, R.A. & Wiggins, R.J.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. BUTTERFLY VALVE CAVITATION TEST

Description: Tests were made on butterfly vaives similar to those used in the discharge leg of each of the three external recirculation loops of the Pathfinder reactor in order to determine the critical values of a dimensionless cavitation number ( /occurred in pu ) used to specify the limits of operation for reactor valves, at incipient cavitation. The experimentally determined values of the cavitation number were used to determine the cavitation-free control range of the Pathfinder valves. The tests showed that both the undissolved and dissolved air content of the water caused cavitation to occur at higher values of sigma. It appeared that cavitation first occurred in the vortices downstream of the valve disk. A limiting cavitation condition was defined for the reactor butterfly valves. (M.C.G.)
Date: March 20, 1963
Creator: Grimm, N.P.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT STEAM SEPARATOR DEVELOPMENT

Description: Development of a steam separator the Pathfinder Reactor is reported. A full-scale separator model was developed through the combination of scale-model testing and the application of principles associated with the existing theory of centrifugal separation. This model was put through full-scale air-water tests which led to modifications and a final design which meets Pathfinder requirements. Design data are included for the reactor and the steam separator. (J.R.D.)
Date: June 15, 1962
Creator: Kutsch, G.C.; Swanson, D.H. & Yant, H.W.
Partner: UNT Libraries Government Documents Department

SMALL POWER REACTOR PROJECTS OF THE UNITED STATES ATOMIC ENERGY COMMISSION

Description: Information on small power reactor projects of the USAEC is summarized. General information concerning the projects as a whole is given. Specific projects discussed include: the Elk River Power Reactor, the Piqua Nuclear Power Facility, the BONUS Power Reactor, the Pathfinder Power Reactor, the small-size pressurized water power reactor, and the experimental low-power process heat reactor. (M.C.G.)
Date: September 28, 1961
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. HYDRAULIC ANALYSIS OF PATHFINDER BOILE. Summary Report

Description: A hydraulic analysis of the Pathfinder boiler core was completed. A description of flow paths including a schematic diagram is included. Pressure drops along primary and leakage fiow paths were calculatsd. After the resistance of each of the leakage paths was identified and the available driving forces in terms of pressure drops associated with the active fiow were established, the leakage rates were easily determined. The dependence of pressure drops on core operating parameters was investigated. The boiler flow rates were also determined. The natural circulation flow rate as a function of power level was estimated at normal condltions of temperature and pressure. The relationships between the boiler parameters of fiow, power, pressure, and inlet subcooling which arise through the laws of conservation of mass and energy are presented. (M.C.G.)
Date: February 15, 1961
Creator: Sher, N.C.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. RECIRCULATION PIPING DESIGN

Description: The coolant recirculation system in the Pathfinder reactor comprises three mixed-flow centrifugal pumps and three piping loops. The design criteria are summarized; and flexibility and stress analyses on the piping are presented, together with a vibration analysis of one pump and loop. The results indicate that vibration should be no problem, that all stresses are within the allowable limits, and that there should be no resonance difficulties during pump operation. (D.C.W.)
Date: January 10, 1964
Creator: Nolan, D.J. & Patterson, J.F.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. IBM-704 PROGRAM FOR REACTOR CONTAINMENT, PRESSURE SUPPRESSION ANALYSIS

Description: A research and development program to investigate the feasibility of eliminating vapor closure for the Pathfinder Reactor was conducted. The major inquiry under the feasibility study involved an analysis of the complex transient conditions occurring in the reactor cavity, the pump rooms, and the entire reactor building following a primary system rupture. To solve the simultaneous nonlinear set of equations evolving from the heat, mass, and force balances in the system, an IBM-704 digital computer program was developed. The program has a very general input and can therefore be used with other containment designs. Input parameters include: initial pressures in reactor and throughout the containment building, hent capacity of vessel, decay heat, feedwater flow rate, enthalpy of feedwater, and volume of primary coolant system. (auth)
Date: July 15, 1960
Creator: Mason, E.E. & Chmielewski, W.M.
Partner: UNT Libraries Government Documents Department

FULL SCALE CLOSURE TEST

Description: The tests performed on a full-scale prototype of the closure designed for the Pathfinder reactor vessel are described. This head was bolted to another head designed to simulate the reactor vessel. The design pressure of the facility is 700 psig at 500 deg F. Strain gages and brittle coatings were used to determine the stresses in the closure. Dial indicator gages were used to measure flange rotation after the head was secured and while it was subjected to hydrostatic pressure. Tests were performed at reactor operating temperature and pressure to evaluate the closure and gasketing. The vessel was thermal cycled, and temperature gradients in the head measured to establish allowable heating and cooling rates. Hydraulically operated bolt tensioners were used to seal and open the closure. Special tools and procedures were developed for underwater operation. (auth)
Date: September 20, 1962
Creator: Patterson, J.F.; Wnuk, S.P. & Bemis, E.A.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. BORON STAINLESS STEEL CONTROL RODS FOR PATHFINDER REACTOR. Final Summary Report

Description: An extensive development, fabrication, and design analysis program was completed on 2 wt% boron stainiess steel for Pathfinder boiler and superheater control rods. Results indicated that the control rods will operate satisfactorily in the reactor under all foreseeable conditions. It was concluded that the maximum local burnup on the boiler rods is limited to 1.0 core at.% and the superheater rods to 0.5 core at.% to remain well below the onset of any deleterious effects. All stresses imposed on the material were found to be below yield strength. The deflections were calculated and were not sufficient to restrict any movement of the cruciform during reactor operations and scrams. A welding development program produced a sound fabrication method for producing the control rods. A prototype rod was extensively tested in the hot control rod drive test, including a large number of scrams. The rod showed no deleterious effects. The rods were designed to accommodate any helium release and swelling that may occur. (M.C.G.)
Date: February 15, 1963
Creator: Patterson, D.A.; Nehrig, D.A.; Klumb, R.H. & Peterson, T.E.
Partner: UNT Libraries Government Documents Department

PRESSURE DROP AND VOID FRACTION EXPERIMENTS IN SIMULATED PATHFINDER BOILER FUEL ELEMENTS

Description: A heat-transfer research and development program is being carried out in support of the Pathfinder boilingwater, integral-superheating reactor. Studies were made of the effects of tube-sheet type spacers on the axial pressure profile in a simulated fuel element. The effect of boiling on the frictional and spacer type pressure losses in a 6-ft long test section was measured. The void fraction in a test section was measured by a fine gamma-ray traversing technique. The flow downstream from a spacer quickly became established except near the bundle entrance. The local radial void distribution in boiling flow over a rod array was non-uniform with a uniform radial power distribution and the over-all integrated void fractions tended to support the homogeneous model. (M.C.G.)
Date: March 1, 1963
Creator: Kangas, G. & Neusen, K.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. CLUSTERED PIN SUPERHEATER LATTICE EXPERIMENTS

Description: Experiments to obtain detailed thermal flux distribution measurements within a unit fuel cell and measurements of sub-cadmium and epi-cadmium U/sup 238/ absorption in the fuel rods are described. These quantities are required for determination of the thermal utilization and resonance escape probability of the fuel loading. (auth)
Date: February 12, 1963
Creator: Selep, A.
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. DESIGN AND OPERATION OF A BOILING AND SUPERHEATING HEAT TRANSFER LOOP

Description: A test loop was designed and fabricated for the study of the heat transfer and fluid flow characteristics of boiler and superheater fuel elements at heat fluxes of 70,000 to 500,000 Btu/hr-ft/sup 2/. The design and operation of the loop are described. D-c resistance heating at low voltages was used. Control, instrumentation, and shakedown tests are discussed. Runs performed to date are described. (D.L.C.)
Date: August 15, 1963
Creator: Jerman, R.B. & Healy, M.
Partner: UNT Libraries Government Documents Department

Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT. Technical Progress Report, April-June 1963

Description: Progress in the development of the Sioux Falls Power Reactor is reported. Information is presented on: reactor physics of first core high-enriched boiler fuel elements; design and performance testing of in-core ion chambers, calibration wire, and monitoring system; testing and inspection of core components; irradiation testing of reactor vessel material; instrumentation development; and startup testing program. (N.W.R.)
Date: September 30, 1963
Partner: UNT Libraries Government Documents Department

PATHFINDER ATOMIC POWER PLANT TECHNICAL PROGRESS REPORT FOR OCTOBER 1959- DECEMBER 1959

Description: >Technical progress on the research and development program being performed in connection with the design of the Sioux Falls Power Reactor is reported. Areas covered in detail include fuel element research and development, reactor mechanical studies, nuclear analysis, chemistry, instrumentation and control, plant safety analysis, feasibility studies, and steam plant and reactor auxiliary systems design. (For preceding period see ACNP-5924.) (W.D.M.)
Date: March 15, 1960
Partner: UNT Libraries Government Documents Department