Pilot plant studies were conducted to develop a continuous process for recovering uranium from nichrome fuels (HTRE). The process consisted of dissolution of fuel in mixed HCl--HNO/sub 3/ solution, removal of the chloride ion by stripping with HNO/sub 3/ in a packed column, and then recovery of the uranium by TBP solvent extraction. Recovery of uranium from nichrome fuels at satisfactory rates and efficiencies can be obtained by this process. Reactor fuels containing large amounts of silica may present a solids problem during chloride removal. Titanium is a suitable material of construction for the dissolver, stripping column, and their associated equipment (feed, off-gas, and product vessels). Stainless steel equipment is suitable for the solvent extraction system. (auth)

Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.

A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to date. (auth)

From summary: "A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to-date."

Criteria and guide lines are presented for the design, construction, and operation of safe, economical, and efficient glove boxes and associated facilities based upon present conditions and anticipated changes. Comprehensive discussion of glove box materials and components, safety and fire prevention methods, health physics problems, operational considerations, and brief descriptions of AEC installations are included. (39 references) (C.H.)

Abstract: This technical report analyzes gamma dose rate and neutron measurements in their relation to the SM-1 shield design and is a continuation of previous shielding measurements and analyses reported in APAE-35 and APAE-35 Supplement 2. The data reported herein are spent fuel element and rod drive pit gamma dose rates. An analysis of gamma dose rates off the core midplane is presented and compared with test data.

The SNAPSHOT Safety Program, as described in this document, is therefore formulated to align safety studies performed by separate agencies and their contractors. At the present stage in program development, the plan is principally concerned with the initial SNAPSHOT flight (SNAP 10A). SNAPSHOT represents a special flight mode for the initial reactors operated in space. The flights are designed to permit early space reactor tests prior to resolving all the safety proglems that may be associated with more advanced programs. Of primary significance is that reactor operation will not be initiated until an orbit of satisfactory lifetime has been obtrained, thus ensuring the long-term decay of the fission products producted prior to re-entry.

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Analyses of clam shells for Sr, Sr/sup 90/, and Ca are reported. The data include 208 Sr, 80 Sr/sup 90/, and 35 Ca analyses. Information on age of the clam and shell weight are also included because the Sr concentration in some shells is affected by age and growth rate. A detailed description of sample treatment and preparation is also included. (auth)

A half-scale clear plastic nonnuclear flow model of the 40-Mw(e) Peach Bottom High-temperature Gas-cooled Reactor (HTGR) vessel and internals was operated during the period from January 1981, through October 1981. The model was operated as an induced system using ambient air as the working fluid. The maximum Reynolds number achieved in the model was approximately one-half of the Reynolds number corresponding to the full-load design conditions in the prototype. The prototype reactor pressure-drop values extrapolated from the flow-model data indicated a pressure drop of 2.0 psi for a helium flow rate of 468,000 lb/hr and pressure of 350 psia, and a constant inlet and Outlet temperature of 650 deg F. The corresponding conservatively calculated pressure-drop value was approximately 2.9 psi. No areas of serious flow starvation were observed within the model during tests with flow through only one nozzle or through both nozzles. The inlet flow divided almost equally into the upward and downward directions. Regions where low velocities were indicated appeared to be turbulent and free from stagnation. Completely closing the four off-center openings in the top head reduced the flow of air from the outer flow jacket to the inner flow jackets by only about 20%. This result …

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.

The green photosynthetic bacteria are characterized by the presence of either chlorobium chlorophyll (bacterioviridin)-65o or chlorobium chlorophyll-66o (numerical designation based on the position of the red-absorption peak in ether) z. Most strains of Chlorobium contain chlorophyll-66o which has its major red peak between 74 ° and 75 ° m/~ in FiFo. KATZ AND WASSINK z first reported an additional minor absorption peak at 81o mF for Chlorobium limicola in vivo and a corresponding minor peak at 780 m F in ethanol extracts. LARSEN (Figs. 6-11 in ref. 3) also observed this 8Io-mF absorption band in another Chlorobium strain and a corresponding peak at 77 ° m/~ in acetone extracts. In strain L of C. thiosulfatophilum the minor red peak appears at 800 mF, clearly resolved from the main peak of chlorophyll-65o at about 725 m/~ (see refs. I, 4). We have observed the minor red peak once again in Chloropseudomonas ethylicum, strain 2K (refs. 5, 6), as a shoulder at about 81o mF on the side of the 75o-mF peak of chlorophyll-66o (ref. 7). The evidence presented in this paper indicates that the absorption peak appearing between 800 and 81o m/, in vivo does not belong to chlorophyll-65 o (or …

Technical report about the investigation of whether low kinetic energy nuclear fission fragment particles create tracks in thin films similar to the tracks created from total kinetic energy fragments in excess of 150 Mev. The research goal is to understand the mechanism of track formation.

This technical report is part four in a series on the structure of sperm whale myoglobin. This report examines the amino acid sequences of the smaller tryptic peptides containing aromatic residues in order to describe in detail the sequences for peptides, tripeptides, and hexapeptides.

Dense partricles of ThO/sub 2/-UO/sub 2/ were prepared by a sol-gel process and vibratorily compacted into metal tubes to a density approaching 9.0 g/ cc. The steps in this method are all simple and can be carried out behind shielding, which is necessary for refabricating U/sup 233/ fuels. The sol-gel process consists of preparing a hydrous thoria sol, adding the U/sup 233/ as nitrate solution, evaporating to a gel, and finally calcining to almost theoretically dense oxide particles at orly 1150 deg C. The sol-gel-prepared oxide, after being sized, was compacted with a simple, inexpensive pneumatic vibrator. (auth)

This report examines radiation damage in solids, looking particularly at calculations and experiments that can provide quantitative predictions of damage.

Technical report that attempts to address the controversy regarding the activation energy for the process of annealing single interstitials in irradiated graphite. The experiments determined that "the activation energy for the process of annealing single interstitials in neutron irradiated graphite and the absolute rate of formation of displaced atoms have been determined..." from the abstract.