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The purpose of this document is primarily to discuss the effects of current retubing programs on the graphite moderator of the K Reactors. A secondary purpose of this report is to present general information related to graphite arrangement and keying patterns at the other operating reactors and to review, in a limited way, the types of graphite distortion observed at these reactors.

Conclusions resulting from a recent corrosion study, together with evidence of graphite damage possibly occurring during retubing operations (having obvious implications in regard to reactor life), initiated a critical assessment of the water treatment process. This study was undertaken to determine whether immediate or near-term process changes could be made at the older reactors to minimize aluminum corrosion without causing adverse effects in other areas.

The EOCR prototype control rod, control rod drive, and driver fuel assembly were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. The modifications required were tested to establish the satisfactory performance of the modified components. Flow versus pressure differential measurements were performed on the driver fuel and the control rod. These measuremerts were also performed on various sized orifices in both assemblies to facilitate final orifice sizing when the final physics and heat transfer calculations have been completed. Scram insertion time curves were obtained for a variety of control rod configurations and test conditions. These curves not only established the scram insertion reliability of the control rod but also provided the basis for performing a control rod force analysis. Included are descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation. (auth)

Report discussing the results of experiments on an EOCR prototype control rod, control rod drive, and driver fuel assembly that were extensively tested in 500 deg F Santowax and 132 deg F water. These tests not only established the operating characteristics of these assemblies but also revealed a number of deficiencies in the various components. It includes descriptions of the control rod, control rod drive, and driver fuel assembly together with descriptions of their method of operation.

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The criteria contained in this report have been established to provide the technical bases for the design modifications involved in the K-Reactor tube replacement. The ultimate intent of these criteria is to provide the basic technical data and concepts to assure: technical feasibility and operability of the reactor system as modified; operation of the reactor and its services to minimize nuclear and radiation hazards; and appropriate lifetime of the reactor and its service facilities as modified. The criteria are appropriately broad and may not contain all the data necessary to accomplish detail design. The information contained herein shall serve as a basis for evaluation and approval of all portions of the modification relating to the process as indicated in the above three points.

The heat exchanger of the calciner consists of a vessel into which unfired, horizontal, bayonet tubes extend in a fluidized bed. Strain measurements were taken on several of the tubes under simulated operating conditions and the associated dynamic stresses were calculated. Vibrations greater than design limitations for indefinite operation were found to exist. To restrict these vibrations and prevent further tube fatigue cracking, a tube support was installed. Since the installation of the support, the calciner has operated satisfactorily over 1275 hours. (auth)

The purpose if this paper is to present tables of perturbed wave functions which have been obtained in three recent investigations: (1) wave functions v1'(nℓ→ℓ') which pertains to the perturbation of the d electrons of various ions as a result of the potential due to a nuclear quadrupole moment Q3 (2) wave functions v1',H(nℓ→ℓ) which represent the antishielding of the d electrons for a possible nuclear hexadecapole moment H; (3) wave functions u2'(ns→p) which pertain to the dipole perturbation of the valence (ns) electrons of the alkali atoms. Throughout this paper, the notation is the same as in a previous report in which a similar tabulation of perturbed wave function was made.

A test report on the brittleness of borated steel to be used in the KIWI B-5 shield capsules.

Molten fluoride salts, because of their radiation stability and ability to contain both Th and U, offer important advantages as high-temperature fuel solutions for nuclear reactors and as media suitable for nuclear fuel processing. Both applications have stimulated experimental and theoretical studies of the corrosion processes by which molten salt mixtures attack potential reactor materials. Corrosion experiments with fluoride salts which were conducted in support of the Molten-Salt Reactor E xperiment and analytical methods employed to interpret corrosion and masstransfer behavior in this reactor system are discussed. The products of corrosion of metals by fluoride melts are soluble in the molten salt; accordingly passivation is precluded and corrosion depends directly on the thermodynamic driving force of the corrosion reactions. Compatibility of the container metal and molten salt, therefore, demands the selection of salt constituents which are not appreciably reduced by useful structural alloys and the development of container materials whose components are in near thermodynamic equilibrium with the salt medium. Utilizing information gained in corrosion testing of commercial alloys and in fundamental interpretations of the corrosion process, an alloy development program was conducted to provide a high temperature container material that combined corrosion resistance with useful mechanical properties. The program …

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Research was continued during the report period on the use of isotope neutron sources for producing short-lived radioisotopes. Experiments with a newly constructed betacounting cell are reported in which a 50-curie Be--Po neutron source was used. Study of the radiation chemistry of polymers was continued concerning the effects of polymer structure on free-radical formation. Free-radical formation in several additional polymers was studied. Preliminary work is also reported in an investigation of internal irradiation effects on the chemical activity of catalysts. (J.R.D.)

A technique has been developed for slow cycle strain fatigue testing using specimens of thin-wall tubing of the type under consideration for use as super heat fuel cladding. Data on type 304 stainless steel have been obtained under radiation and in the absence of radiation. The strain cycle fatigue life of this alloy at 1200 to 1300 deg F is decreased three fold by the presence of a neutron flux of 1.5 x 10/sup 14/ > 1 Mev. Out-of-reactor data have been obtained on Inconel at 1300 deg F. (auth)

Technical report describes how glasses and crystals subjected to ionizing radiation develop absorption bands and become colored. The coloring of defects can be used to determine how nuclear reactor induced defects anneal out or disappear as an irradiated sample is heated.

Technical report investigates creating a microbeam of deuterons to simulate cosmic rays and the results of brain irradiation, irradiation of the eye, and irradiation of hair follicles of mice. The report's conclusion was that "astronauts exposed to heavy primary particles over a period of some weeks would be expected to develop gray hairs, but this is the only significant biological damage they would suffer."

This technical report introduces "some approximations into the basic quantum mechanical theory" so that the theory of the covalent bond and the molecular orbital method "can be combined into one which will yield quantitative rather than qualitative binding energies and cohesive energies and also distinct energy levels and band structure." This approach will provide a common method "suitable to both solid state physicists and physical chemists, for calculating the energy levels in metals and complex molecules." This report also contains figures detailing the findings. (Quotations taken from introduction)

This technical report introduces a new method to capture entire cell populations in the intestines of rats, which have been continuously exposed to radiation.This report finds that the "total number of cells per crypt found after 5 days of irradiation decreases with increasing dose rate." This report includes four figures and two tables detailing findings.

Technical report covering an extensive investigation of the nature of fission fragment "damage" in various metals. During the investigation electron micrographs of fission fragment tracks in the BNL Graphite Reactor fuel element cores were made.

Technical report which reports a study of the effects of extinction upon diffuse x-ray measurements.

Technical report summarizing the evidence that "the capacity for spontaneous tumor formation is certain Nicotiana hybrids is genetically controlled and that genetic change during plant development, i.d. somatic mutation, is not causal to tumor formation." from the introduction.

Technical report that investigates the the correlation between changes in catalytic activity caused by high energy radiation and the changes in the physical and chemical structure of magnesium oxide catalysts. The investigation of magnesium oxide catalysts might help clarify a complex and poorly understood field.