Call Number (LC) Title Results
E 1.99:in--1158 ISOTHERMAL HYDRAULIC MEASUREMENTS IN FUEL ELEMENTS IN ATR CORE. 1
E 1.99:in--1159 VERSATILE SPECTROPHOTOMETRIC METHOD FOR THE DETERMINATION OF MICROGRAM AMOUNTS OF MERCURY. 1
E 1.99:in--1160 IRRADIATION TESTING OF FUEL FOR THE MARK I CORE OF THE ARGONNE ADVANCED RESEARCH REACTOR. 1
E 1.99:in--1169 APPLICABILITY OF CONVENTIONAL PROTECTIVE COATINGS TO REACTOR CONTAINMENT BUILDINGS. 1
E 1.99:in--1170 APPLICABILITY OF CHEMICALLY REMOVABLE COATINGS TO REACTOR CONTAINMENT BUILDINGS. 1
E 1.99:in--1172 FISSION PRODUCT BEHAVIOR UNDER SIMULATED LOSS-OF-COOLANT ACCIDENT CONDITIONS IN THE CONTAMINATION--DECONTAMINATION EXPERIMENT. 1
E 1.99:in--1173 CRITICALITY ASPECTS OF THE REVISED ZIRCONIUM DISSOLUTION SYSTEM AT THE IDAHO CHEMICAL PROCESSING PLANT. 1
E 1.99:in--1176 METALLURGY AND HOT CELL BRANCH EQUIPMENT CAPABILITIES MANUAL. 1
E 1.99:in--1177 MATHEMATICAL MODEL FOR PREDICTING HEAT TRANSFER CHARACTERISTICS OF A BAYONET TUBE. 1
E 1.99:in--1178 BURNUP DETERMINATION OF NUCLEAR FUELS. Project Report for the Quarter, April 1--June 30, 1967. 1
E 1.99:in--1179 A PRIMARY STUDY ON THE COMPRESSIVE PROPERTIES OF COMPOSITE NUCLEAR FUEL PLATES. 1
E 1.99:in--1181 DESCRIPTION OF THE PILOT PLANT FOR THE HEADEND REPROCESSING OF UNIRRADIATED ROVER FUELS. 1
E 1.99:in--1182 AN EVALUATION AND COMPILATION OF ²³⁷Np CROSS SECTION DATA FOR THE ENDF/B FILE. 1
E 1.99:in--1184 TURBO-40 A TWO-DIMENSIONAL NUCLEAR REACTOR DEPLETION PROGRAM FOR THE IBM 7040-44 COMPUTER. 1
E 1.99:in--1185 CORROSION EXPERIENCE WITH TYPE 316 STAINLESS STEEL IN SODIUM--POTASSIUM EUTECTIC ALLOY AT 1400°F. 1
E 1.99:in--1186 ATR PRIMARY COOLANT SYSTEM CHECK VALVE PROBLEM ANALYSIS AND CORRECTION. 1
E 1.99:in--1186(suppl.1) ATR PRIMARY COOLANT SYSTEM CHECK VALVE PROBLEM ANALYSIS AND CORRECTION. 1
E 1.99:in--1189 BURNUP DETERMINATION OF NUCLEAR FUELS. Project Report, July 1--September 30, 1967. 1
E 1.99:in--1191 PERFORMANCE OF TITANIUM AND NIOBIUM ELECTRODES IN AN ELECTROLYTIC DISSOLVER FOR NUCLEAR FUELS. 1
E 1.99:in--1192 THE PHYSICAL PROPERTIES OF NITRATE SOLUTIONS OF EBR-II FUEL ELEMENTS. 1