REACTOR TECHNOLOGY REPORT NO. 9--ENGINEERING
Reactor Design. Tests were conducted to observe visually and to photograph the phenomenon of reactor parallel-plate fuel assembly collapse and to witness inlet flow conditions. The effect of flow redistribution on the critical flow velocity for collapse of reactor parallel-plate fuel assemblies was investigated. An extensive series of tests was conducted on the flowinduced vibration and resultant wear in twisted-ribbon fuel elements. Discontinuity stresses between cylinders of unequal thickness were investigated. A full-size reactor pressure vessel, for a pressurized water reactor, was subjected to controlled heating and cooling cycles at design pressures and temperatures. The test was designed to simulate heat transfer conditions existing in an actual reactor insofar as they affected the prcssure vessel. Use of a 4-in.-ID thin- walled part of AISI 4l0 stainless steel tempered at 650 deg F to hardness RC36-42 as a pressure-rethining member in a high temperature, high purity, water environment was studied. The construction of an Inconel corrosion testing faciliiy is reported. Heat Transfer and Fluid Flow Analysis. Data are presented for a class of reactor fuel elements that have strong secondary flows and strongly skewed boundary layer flows. Tests to measure twisted-ribbon fuel element temperatures at high fluxes and low pressures were completed. Departure from nucleate boiling tests were conducted on oval twisted ribbons with upflow of water at 2000 psia. Power Plant Component Design. The development and testing of a model dashpot for retarding the closure of a specific swing-type check valve used in the main coolant loops of a pressurized-water nuclear power plant are described. Strain cycling tests are reported on large specimens of AISI type 347 stainless steel and 2/4 Croloy. The pressure stresses at the junction between a support skirt and pressure vessel were investigated. The post-yield bending of rectangular sections was investigated. A digital computer solution is presented for axisymmetric loads and temperature distributions in cylinders. Irradiation Testing. A creep-test facility was developed to test irradiated samples with the accuracy obtained on non-irradiated samples. Design problems of the fixed gas annulus irradiation capsule are discussed. The design of a constant temperature irradiation capsule is presented. The design of high temperature density measuring equipment is reported. Results of neutron flux monitoring of in-pile irradiations are presented. (For preceding period see KAPL-2000-5.) (W.L.H.)
- Research Organization:
- Knolls Atomic Power Lab., Schenectady, N.Y.
- DOE Contract Number:
- W-31-109-ENG-52
- NSA Number:
- NSA-13-017312
- OSTI ID:
- 4225297
- Report Number(s):
- KAPL-2000-6
- Resource Relation:
- Other Information: Orig. Receipt Date: 31-DEC-59
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
ALUMINUM ALLOYS- CHROMIUM ALLOYS- CONFIGURATION- COOLING- CORROSION- CYLINDERS- FLUID FLOW- FUEL ELEMENTS- HEAT TRANSFER- HEATING- INCONEL ALLOYS- MECHANICAL STRUCTURES- NICKEL ALLOYS- NIOBIUM ALLOYS- - PLANNING- PLATES- PRESSURE VESSELS- REACTORS- STAINLESS STEELS- STRESSES- TEMPERATURE- TESTING- THICKNESS- TITANIUM ALLOYS- VELOCITY- VIBRATIONS- WATER COOLANT- WEAR
CHROMIUM ALLOYS- CLOSURES- COMPUTERS- CONTROL- COOLANT LOOPS- CROLOY- CYLINDERS- DEFORMATION- DIGITAL SYSTEMS- DISTRIBUTION- MECHANICAL STRUCTURES- PLANNING- POWER PLANTS- PRESSURE- PRESSURE VESSELS- REACTORS- STAINLESS STEELS- STRESSES-