Document Details
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Title:
QUARTERLY PROGRESS REPORT - FUELS DEVELOPMENT OPERATION - JULY, AUGUST, SEPTEMBER 1956
Author(s):
Subject Terms:
(HOLLOW) - DESIGN(HOLLOW) - TESTING(MG-U) - DESIGN(U COMPACTS) - TESTINGALLOYS - X-RAY DIFFRACTION ANALYSISALUMINUMALUMINUM - BONDINGALUMINUM-SILICON SYSTEMS - DIFFUSIONANNEALINGCOMPONENT PREPARATIONCRYSTAL STRUCTUREDESIGNDIFFUSIONELECTRON MICROSCOPYENGINEERING TEST REACTORFAILURE IN REACTORSFUEL FABRICATIONFUELS AND MATERIALS ENGINEERINGHARDNESSHEAT TRANSFERHIGH TEMPERATURE REACTIONSHYDROGENKRYPTON - DIFFUSIONLABORATORIESMAGNESIUM-URANIUM COMPACTSMECHANICAL PROPERTIESMETALS - CASTINGMOLYBDENUM - CRYSTAL STRUCTUREN MICROSCOPYPHYSICAL PROPERTIESRADIATION EFFECTSRECRYSTALLIZATIONROLLING MILLSSERVO-MECHANISMSSLUG CANNINGSLUG ELEMENTS (CLUSTER) - TESTINGSLUG ELEMENTS (UO2) - TESTINGSLUG ELEMENTS - INSPECTIONSLUG ELEMENTS - THERMAL CONDUCTIVITYSLUGS (MG-U)SORPTIONSTAINLESS STEEL - BONDINGSTEAMTEMPERATURE EFFECTSTESTINGTHERMAL RADIATIONTHERMAL STRESSESTHERMOCOUPLES - RADIATION EFFECTSTHORIUM-URANIUM ALLOYSTIN ZIRCONIUM ALLOYS - THERMAL CONDUCTIVITYTIN-ZIRCONIUM ALLOYS - ELECTRIC CONDUCTIVITYURANIUMURANIUM (IV) OXIDES - FABRICATIONURANIUM - CHEMICAL PROPERTIESURANIUM - FRACTUREURANIUM - TENSILE PROPERTIESURANIUM-ZIRCONIUM ALLOYS - TENSILE PROPERTIESVACUUM FURNACESWATERWELDINGWELDING - EQUIPMENTXENON - DIFFUSIONZIRCONIUM - CHEMICAL PROPERTIESZIRCONIUM - X-RAY DIFFRACTION ANALYSISZIRCONIUM ALLOYS - RECRYSTALLIZATION
Document Location:
DOE Public Reading Room - Hanford Battelle P.O. Box 999 MS H2-53 Richland WA 99352 (509)372-7443
Document Type:
REPORT
Publication Date:
1956 Oct 23
Declassification Date:
1992 Oct 26
Declassification Status:
Declassified
Document Pages:
87
Accession Number:
RL-1-364610
Document Number(s):
HW-46091
Originating Research Org.:
GE - HAPO
OpenNet Entry Date:
2004 Feb 24
OpenNet Modified Date:
2015 Jun 26
Description/Abstract:
(PAGE 3.1-3.22) PHYSICAL METALLURGY (1) OPTICAL AND ELECTRON MICROSCOPY (2) ELECTRON MICROSCOPY AND X-RAY DIFFRACTION OF IRRADIATED ZR AND ZR ALLOYS (3) FRACTOGRAPHIC STUDIES ON U (4) FISSION PRODUCT MOBILITY EXPTS (DIFFUSION OF XE AND KR IN METALS) (5) DIFFUSIN STUDIES - EFFECT OF RADN ON U DIFFUSION INTO AL, ACSI, AND ZR (DATA ARE TABULATED FOR U INTO ALSI AND ALSI INTO U) (6) RADN EFFECTS ON ZR AND MO CRYSTAL STRUCTURE (7) STUDY OF IRRADIATED THERMOCOUPLES (8) EFFECT OF TRANSITION COOLING RATE ON THE ACTIVATION ENERGY REQUIRED FOR ALPHA PHASE RECRYSTALLIZATION OF U (9) SORPTION OF HW BY ZR UNDER VARIOUS EXPOSURE CONDITIONS. (PAGE 3.22-3.34) PHYSICAL METALLURGY CONT'D (10) REACTIONS (A) ZR WITH DRY STEAM AT ATMOSPHERIC PRESSURE (B) ZR WITH DRY STEAM AND MOLECULAR H (C) ZR WITH H IN A DEFECTED AL CAPSULE (D) AL-CLAD, ZR AND H SUPPLIED BY OXIDN OF U (E) ZR, STEAM, AND H GENERATED BY OXDN OF U SOT WELDED TO ZR (F) 265C H2O, H, AND ZR UNDER PLASTIC STRAIN (G) ZR, STEAM, AND H UNDER CYCLIC HEATING (11) RECRYSTALIZATION AND RECOVERY OF ZR ALLOYS (A) HEAT TREATMENT (B) RECOVERY OF MECH. PROPS. (C) RECOVERY OF ELECT RESISTIVITY - ZIRCALOY-3 (12) MECH. AND PHYS PROPS. OF IRRADIATED MATERIALS (A) DEPLETED U (B) HOT PRESS BANDS (C ) THERMAL CONDUCTIVITY OF ZIRCALOY-2, U , AND U-1.5 W/O ZR (D) ZIRCALOY-2 TENSILE SPECIMENS (13) CAPSULE IRRADNS AT MTR-TENSILE PROPS OF IRRADIATED U. (PAGE 4.1-4.7) METALLIC FUEL DEVELOPMENT (1) CLUSTER FUEL ELEMENT TESTING (2) SPOT WELDED CLUSTER FUEL ELEMENT SUPPORT SPIDERS (3) THERMAL COND OF BOND REGION BETWEEN FUEL AND JACKET OF A SLUG (4) A NEW METHOD OF CALCG THE THERMAL STRESSES IN CYLINDRICAL ELEMENTS (5) HEAT TRANSFER BY THERMAL RADN (6) HANFORD SIZE U-MG FUEL ELEMENTS (7) HANFORD SIZE CORED INSULATED SLUGS (8) COAXIAL TUBE FUEL ELEMENT DESIGN (9) FUEL ELEMENT GEOMETRY STUDIES. (PAGE 4.8-4.9) METALLIC FUEL DEVELOPMENT (10) SLUG INSPECTION REJECT RATE VS PILE FAILURE RATE (11) EVALUATION OF SEP VACUUM HOT PRESSED SLUGS (12) EVALUATION OF EXPTL FUEL ELEMETNS (13) JOINING OF AL TO SS'S (14) RESISTANCE SPOT WELDING OF PROJECTION FUEL ELEMENTS (15) VACUUM BRAZE CANNING (16) AL COMPONENT PREPN FOR HOT PRESS (EFFECT ON STRENGTH OF BOND) (17) I AND E COOLED WAFER FUEL ELEMENT IRRADN IN MTR (18) ETR FUEL ELEMENT TESTING FACILITY (19) POWDER METALLURGY U-MG FUEL MATERIAL (20) TH-U ALLOY (21) U-SHOT AND U-MG MATRIX FUEL (22) EFFECT OF ZIRCALOY CLADDING ON HIGH TEMPERATURE H2O CORROSION OF U OR REACTION OF FUEL RODS WITH HIGH TEMPERATURE H2O (PAGE 5.1-5.9) CERAMIC FUEL MATERIALS (1) CERAMICS LAB (2) FABRICATION OF UO2 (3) TOLERANCE EXPT - GEH-3-19 (ZIRCALOY CAPSULE CONTAING A SINTERED UO2 CORE HAS BEEN IRRADIATED - GIVES PRELIMINARY EXAMN RESULTS). FACILITEIS AND EQUIPMENT (1) VACUUM WELDING BOX (2) VACUUM MANIPULATOR (3) CENTRIFUGAL CASTING (4) TRAVELING VACUUM TUBE ANNEALING FURNACE (5) HOT HARDNESS TESTER (6) ROLLING MILL FOR PYROPHORIC AND TOXIC MATERIALS.