| Call Number (LC) | Title | Results |
|---|---|---|
| E 1.99:conf-690910-- |
High temperature thermal cycling and drift test of W{sub 95} Re{sub 5} versus W{sub 74} Re{sub 26} thermocouples Flowing sodium capsules in the General Electric Test Reactor Observation of fuel failure behavior during in-pile meltdown tests using high-speed photography and a transparent autoclave Capsules and sodium loops used in Argonne National Laboratory reactor safety experiments in the TREAT Reactor Instrumented subassembly system and in-core instrument test facility for EBR-II Characterization of advanced irradiation testing vehicles for EBR-II. Xenon tagging of instrumented fuel capsules for use in EBR-II. Use of the Thermal TREAT Reactor for Fast Reactor Safety Studies Reactor factility for neutron irradiations at temperatures ranging from -193 to 725 deg C Assemblies for thermal and fast flux irradiation of (UPu)N fuels Damage-function analysis of neutron-energy and spectrum effects upon the radiation embrittlement of steels Neutron radiographic inspection of irradiated SNAP fuel Design of a lead-type capsule system to investigate the radiolysis of water Pycometer, profilometer, and laser puncturing for space reactor fuel capsule examination Experience with instrumented capsules for high temperature irradiation of fuel forms Achieving uniform specimen temperatures in an irradiation capsule using heat pipes CRICET, a system for remote measurement of fuel-element temperatures Unrestrained swelling and fission gas release experiments System for calculation of fission power in irradiation tests In-pile gamma dosimetry measurements with oxalic acid Compact 30 KW circulating helium capsule for fuel element tests in NASA Plum Brook reactor Influence of neutron spectrum on helium atom generation in stainless steels Some applications of neutron radiography in irradiation testing technology Remote encapsulation and TREAT capsule handling techniques Techniques and apparatus for inspection, handling and annealing in highly radioactive fuel microspheres Continuous monitoring of fission gas release during irradiation of nuclear fuel specimens Development of fission gas pressure transducers at Argonne National Laboratory Fast reactor fuel testing in forced convection capsules Grooved melt wires for temperature measurement of reactor fuel Experiment design studies for fuel pin development Use of nuclear explosions for the study of radiation damage processes Capsule design for dynamic in-pile friction experiments Decay heat generation and removal from fuel test bundles Post-irradiation analysis of high temperature, low burnup tungsten UO{sub 2} test plates A doubly telescoping design of a nuclear reactor experiment containing eight variables Apparatus for measuring in-pile creep of LMFBR candidate fuels Development and feasibility tests of isothermal irradiators Fatigue specimen capsules, EBR-II MARK B-& subassembly A microprobe study of the retention of the fission gas xenon in irradiated uranium fuels dispersed in alumimum-clad nuclear reactor fuel plates National symposium on developments in irradiation testing technology, September 9-11, 1969, NASA Lewis Research Center, Sandusky, Ohio Recent advances in fast-response miniature neutron flux monitors Design and in-pile operation of instrumented hydraulic capsules Fast reactor sodium-bonded fuel rod evaluation in a thermal reactor Retractable-replaceable thermocouple for in-pile experiments Measurement of internal pressure buildup in full-sized fuel rods during irradiation |
45 |
| E 1.99: conf-690910--1 | Concept for a gas buffered annular heatpipe fuel irradiation capsule | 1 |
| E 1.99: conf-690910--2 | Irradiated fuel examination and measurement | 1 |
| E 1.99: conf-690910--3 | Measured energy deposition rates for various nonfissionable materials in a nuclear reactor environment | 1 |
| E 1.99: conf-690910--4 | Irradiation studies of uranium nitride | 1 |
| E 1.99: conf-690910--5 | Post-irradiation microanalysis | 1 |
| E 1.99: conf-690910--6 | Analysis of the validity of fast reactor fuel tests in existing test reactors | 1 |
| E 1.99: conf-690910--7 | Reliability of high-temperature thermocouples in irradiation capsules | 1 |
| E 1.99: conf-690911--3 | SINGLE PION PHOTOPRODUCTION IN THE RESONANCE REGION. | 1 |
| E 1.99:conf-690916--(vol.1) | Proceedings of the chemistry symposium [Chandigarh, September 23-26, 1969]. Volume 1. Invited talks and invited papers | 1 |
| E 1.99:conf-690916--(vol.2) |
Proceedings of the chemistry symposium [Chandigarh, September 23-26, 1969]. Volume II. Contributed papers Laboratory investigations in non-aqueous process chemistry Investigations on the process chemistry of neptunium |
3 |
| E 1.99: conf-690921--4 | THE BERKELEY SYNCHROCYCLOTRON IMPROVEMENT PROGRAM. | 1 |
| E 1.99: conf-690924--3 | CYCLOTRON SIMULATION OF NEUTRON-TRANSMUTATION PRODUCED GASES IN REACTOR CLADDING AND STRUCTURAL MATERIALS. | 1 |
| E 1.99: conf-690926--1 | TOTAL CROSS SECTIONS IN MOLECULAR CHARGE TRANSFER REACTIONS WITH DIATOMIC NEUTRALS. | 1 |
| E 1.99: conf-690927--2 | OXYGEN TRANSPORT PROPERTIES OF RARE EARTH OXIDES. | 1 |
| E 1.99: conf-690942--2 | TOTAL BURN SPECTROGRAPHIC ANALYSIS OF PLUTONIUM OXIDE. | 1 |
| E 1.99: conf-690953--1 | INFORMATION STORAGE AND DATA MANIPULATION IN SCINTISCANNING. | 1 |
| E 1.99:conf-690954 | TECHNICAL PAPERS OF THE 23rd METALLOGRAPHIC GROUP MEETING HELD SEPTEMBER 11- -12, 1969, SAN FRANCISCO, CALIFORNIA. | 1 |
| E 1.99:conf-690954-- | HOT CRACKING IN WELDMENTS OF HAYNES ALLOY NO. 25. | 1 |
| E 1.99: conf-690958--1 | EXPERIMENTS ON PARITY NON-CONSERVATION IN NUCLEAR FORCES. | 1 |
