The initial and long-term nuclear characteristics of two internally cooled heterogeneous, graphite-moderated, two-region, molten-salt reactors have been studied. These reactors have doubling times of 22.5 years and 27.5 years. Methods of decreasing the doubling times by removing the Pa233 from the core and be increasing the specific power of the reactor are described.

Samples containing 5 to 10 mg of uranium were extracted with hexone (methyl isobutyl ketone) and titrated coulometrically in sulphate media. Relative standard deviations of 0.45% for samples containing 5 mg and 0.56% for 10 mg were determined by precision studies.

At present, emphasis is being given the application of nondestructive testing to the inspection of nuclear fuel in conjunction with complete product specifications. The objective is to quantitatively specify fuel quality parameters, and to measure the entire fuel production against these specifications nondestructively. Under this concept the acceptability of a given fuel element becomes a well-defined factor readily determined by appropriate nondestructive tests.

Abstract. Spectrographic procedures for determining small amounts of the common contaminants in beryllium and its compounds are described. Suggestions relative to the preparation of synthetic standards are also given.

A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review

A report regarding irradiation behavior of uranium monocarbide fuel experiments NAA 81-3 and AI 3-12

Annual report of the Texas Racing Commission describing goals, activities, and accomplishments during fiscal year 2008.

this report contains topics such as How the Lemon Law Works, What Should a Lemon “Owner” Do?, What Does It Cover?

Annual report of the Texas Racing Commission describing goals, activities, and accomplishments during fiscal year 2009

This technical report provides a general description of the Brookhaven National Laboratory, describing the nuclear characteristics of the Brookhaven reactor and more detailed descriptions of the features and instrumentation of the reactor.

Previous studies by Behrens have provided evidence of systematic behavior in neutron-induced fission cross sections in the incident neutron energy range 3 to 5 MeV. Recently measured fission cross-section ratios revealed this behavior. In this report, these measurements and those of others are used to illustrate the behavior of fission cross sections over the neutron energy range 0.1 MeV to 15 MeV. Similar trends are seen at 0.0253 eV, as revealed by thermal cross-section measurements. 12 figures.

The suitability of Tophet C-Alloy 52/Kovar weldments to hydrogen embrittlement were investigated because of their potential as candidate materials in fabrication of minaturized initiators for pyrotechnics. Cathodic charged samples were statically loaded for extended periods of time resulting in no load failures and in ductile fracture surfaces indicating resistance to hydrogen embrittlement. 20 figures.

Reduced instrument responses are presented for Thermal-Hydraulic Test Facility (THTF) test 100, which is part of the ORNL Pressurized-Water-Reactor (PWR) Blowdown Heat Transfer Separate-Effects Program. The objective of the program is to investigate the thermal-hydraulic phenomenon governing the energy transfer and transport processes that occur during a loss-of-coolant accident in a PWR system. Test 100 was conducted to investigate the response of heater rod bundle 1 and instrumented spool pieces with flow homogenizing screens to a double-ended rupture with equal break areas at the test section inlet and outlet. The primary purpose of this report is to make the reduced instrument responses during test 100 available. The responses are presented in graphical form in engineering units and have been analyzed only to the extent necessary to assure reasonableness and consistency.

The web growth investigation portion of this program was spent in growing a backlog of primitive dendrites and developing a number of dendritic seed crystals having a variety of twin plane spacings. These seeds are to be used in the determination of the optimum twin spacing for dendritic-web growth. Having determined the optimum twin spacing for the seed dendrites, the optimized seeds will be used in the experimental part of the investigation to determine the limitation on the growth width and pull rate of the dendritic-web section. Primitive dendrities containing 2,3,4, and 5 twin planes with twin plane spacings of 0.6 to 19.2 mm. have been grown. A supply of dendrite seed crystals have been grown from these primitive dendrites. Computer programs have been developed that appear adequate for the thermal analysis of the dendritic-web growth. A preliminary two dimensional thermal model of the melt, crucible, susceptor and lid has been completed and numerical results obtained. In this model only radiation heat transfer was assumed for the lid. The temperature profiles obtained were thus lower than is found experimentally in the furnace. The characterization experiments have all been tested and found adequate for characterization of the material grown in the …

The thickness of alumina armor plate is determined which will stop a 10-g steel projectile traveling at 2.1 and 3.0 mm/s.

The tests conducted on the 1/5-scale BWR Mark I pressure suppression test facility simulate the three-dimensional transient conditions that are encountered in a wetwell pressure suppression system during a hypothetical loss-of-coolant accident (LOCA). Specifically, the nitrogen (N2)-driven air clearing phase tests discussed here were performed to obtain the air/water-induced dynamic vertical load function and to determine the response of a 90/sup 0/ sector of a 360/sup 0/ torus structure.

List of the Effective Screening Levels used by the Texas Air Control Board to examine air pollution in 1992.

Report discussing the influence of Fyodor Dostoevky's writings on the work of Nathalie Sarraute.

An archaeological excavation was conducted at the site of proposed groundwater monitoring well 199-K-131 in support of the 100-KR-4 Pump-and-Treat Project between June 2 and 3, 2004. Excavations confirmed that there were no intact cultural deposits at the proposed well location. This report was prepared to document the findings of the test excavation.

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The primary objective of the study is to develop a computer model for a base line direct coal liquefaction design based on two stage direct coupled catalytic reactors. This primary objective is to be accomplished by completing the following: a base line design based on previous DOE/PETC results from Wilsonville pilot plant and other engineering evaluations; a cost estimate and economic analysis; a computer model incorporating the above two steps over a wide range of capacities and selected process alternatives; a comprehensive training program for DOE/PETC Staff to understand and use the computer model; a thorough documentation of all underlying assumptions for baseline economics; and a user manual and training material which will facilitate updating of the model in the future.

This Technical Data Summary comprises the technical information that has been developed to date for the preparation by extrusion cladding of the outer plate of the contemplated Mark IIIA fuel plate bundle. The Mark IIIA fuel bundle is designed to produce plutonium at higher power levels than is possible with the Mark I or Mark VII assemblies. The Mark IIIA and Mark V designs are being developed concurrently for the same purpose. The information, however, on the Mark IIIA design is at present far more complete than for Mark V, and equipment for producing Mark IIIA in test quantities is already available. The purpose of this Technical Data Summary is to have available the facilities for cladding, by an apparently attractive process, a Mark IIIA plate.

High Level Waste supernates are hazardous due to the presence of small quantities of mercury, chromium, lead, silver and barium. The fate of these components based on process knowledge was evaluated. The supernates were grouped into Traditional (normal storage and evaporation), Dilute (stored in Type IV tanks), and Sludge Processing categories, and a review of the limited quantity of available sample data for each type of supernate was performed. The maximum concentration of each hazardous constituent was determined. The most restrictive hazardous constituent in Traditional and Sludge Processing supernates was determined to be mercury, and the most restrictive component in Dilute supernate was chromium. Containers of solid waste contaminated with these supernates must be manifested as nonhazardous before disposal as Low Level Waste in the engineered vaults in the EAV. A method was developed to screen waste containers in order to identify those containers that are nonhazardous. A criterion for {sup 137}Cs content was arbitrarily set to 0.1 Ci, and the volume of supernate required to deposit 0.1 Ci was calculated. Containers with less than 0.1 Ci of {sup 137}Cs and over 85 lb of solid waste contaminated with supernate from normal storage and evaporation operations are nonhazardous. Containers with …

The interaction of tritium with metals is made complex by two phenomena. The first is that the beta decay in the metal produces {sup 3}He. The helium moves to form bubbles. This report shows that growth of the bubbles produces a two-stage swelling of the metal that comes first from the appearance of the helium and second from the relaxation of the lattice disorder. The second phenomena is the steady state ion and free radical concentration in the tritium over gas that interacts with impurities on the metal surface. This report shows that the reaction rates are much faster than for normal hydrogen cleaning.