Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.

Introduction: The objective of the study was to estimate the worldwide distribution of a few broad categories of naturally occurring materials found on the land surface of the earth.

Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.

Foreword: This report describes the results of a series of engineering evaluation studies conducted between July 1, 1961 and June 30, 1962, related to heavy water moderated power reactor plants.

From foreword: This report investigates the economics and performance of alternate cycles for heavy water moderated power reactors.

Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).

Abstract: A rotary kiln was evaluated for the controlled oxidations of UC.

Abstract: The design and initial test of cutting and welding equipment developed to remotely cut and re-weld the bottom process tube joint are discussed in this report.

The following report is the final safety analysis report for the Task 2 Radioisotope Powered Thermoelectric Generator prepared by The Martin Company. It presents analyses, tests and evaluation of the operational safety criteria for the generator.

"A series of high urania-content glasses were fiberized and examined for high-temperature strength properties. One glass, RX360 containing 60% U/sub 3/O/ sub 8/ by weight, had better high-temperature tensile properties than any glass previously reported. It was observed that many of the glasses studied separated into immiscible phases and that the fiberizable glass phase had lower U/sub 3/O/ sub 8/ content than the base compositions. A physical analysis of crystal structures of the devitrification products from the nuclear fuel glasses indicated that most of the crystals consisted of uranium oxide in a reduced state. By adding O/sub 2/ to molten glass, it was possible to eliminate most of this devitrification. By elimination of crystals, the fiberizing of the glass was more uniform and the glasses produced had more consistent physical properties."

Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.

"Properly designed and fitted respirators have been effective devices for reducing the inhalation of toxic aerosols. The degree of protection afforded by these devices has not been quantitatively measured under actual work conditions except by bioassay or other elaborate techniques. This report describes a new quantitative technique for evaluating over-all respiratory performance under conditions comparable to exposure to highly toxic radioactive materials such as plutonium and non-radioactive materials such as beryllium."

From Introduction: "Following the guidelines established by this committee, several commercially developed precision connectors have appeared on the market which have led to the wide use of the precision coaxial lines as immittance standards. This paper has been prepared to alleviate this situation by providing graphs from which the electrical parameters of the lines may be determined rapidly and accurately."

Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were conducted on the open seven control rod array employing 38 stationary fuel elements. Activation measurements consisted of neutron flux measurements using uranium fission foils for relative power distribution studies, the effect of flux suppressors on reducing power peaks, blocked coolant channel measurements, and gamma ray dose distribution. Reactivity measurements were performed to determine the effect f flow divider, flux suppressors and stimulated high temperature and pressure operation; b-10 loading in the SM-2 core; and core material coefficients. For the later, the worth in cents per gm or cents per cc was determined at simulated temperature of 510 degree F for B-10, U-235, stainless steel, and void. Stuck rod measurements were made to obtain an indication of the criticality margin in the …

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.

Report issued by the Brookhaven National Laboratory discussing bulk grain irradiators. As stated in the abstract, "this report presents the results of a study to conceive, evaluate, review and estimate costs for a number of suitable designs for a Cobalt-60 Bulk Grain Irradiator; select a preferred type; and establish required criteria for future detail design and construction of the selected concept" (p. ii). This report includes tables, and illustrations.

A report regarding Unicorn - a program used to calculate point cross-sections from resonance parameters.

Report describing Hanford Laboratories' second report regarding thin wall tubing tests. This part covers "the production [of] test equipment developed, its operation, and test results" (p. 2).

In the Sulfex process, stainless steel cladding, generally 304-L, is removed from fuel elements by dissolution in boiling four to six molar sulfuric acid. When cladding removal is complete, the decladding solution is removed is removed to waste. The exposed fuel cores are rinsed and dissolved in nitric acid.

This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.

From foreword: This report is concerned with the investigation of an indirect cycle plant which was the subject of a joint study between Sargent & Lundy and NDA.

From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.