A method for monitoring radiation damage irradiations using the change of the electrical conductivity of graphite is described. Results of monitoring operations in a number of locations are given. An attempt is made to explain the damage rate found in the converter at CP-3. An estimate of the flux spectrum in VT-4 and the converter of CP-3 is made and the damage rate is computed according to theories of Seitz and James. It is found that the experimental results are more in accord with the predictions of Seitz. A number of corrections to James' report, ORNL-307, are noted in an appendix. It is shown that some information about the fast flux spectrum can be inferred from the radiation damage rate.

The author proves the mean ergodic theorem for nonlinear non-expansive mappings in Banach spaces, extends it by a different argument, deduces several consequences, and points out open problems.

Argonne National Laboratory (ANL) is engaged in a project to determine the impact of advanced scientific computers on Argonne's computing workload. The CRAY-1 was chosen to begin our investigation because it was the only machine currently available that qualifies as an advanced scientific computer, or Class VI (one capable of executing 20 to 60 million floating point operations per second).

The radioactive content of samples of rain, surface water, soil, plants, and material from the beds of surface waters (bottom silt) which were collected and analyzed during 1953 are given in this report. Samples were collected form the Laboratory site, at locations with 25 miles, and at places 100 miles from the Laboratory. Since Laboratory waste water is discharged into Sawmill Creek, water from the this stream was analyzed daily. Other samples were collected from the Laboratory site periodically, and collections from the off-site locations were made at approximately quarterly intervals. Most of the results were obtained by counting total alpha and beta activity; selected samples were analyzed for specific nuclides and elements. The total activity measurements provided a rapid means of determining general levels of radioactivity which could be compared between samples and indicated which samples should be analyzed in more detail. Radioactive contamination attributable to Laboratory operations was found only in water and bottom silt taken from Sawmill Creek below the outfall of Laboratory waste water (below site).

THI3D-1 is an improved version of the THI3D computer program for steady-state, single-phase, thermal-hydraulic multichannel analysis. The program accounts for conservation of mass, energy, and momentum subject to pressure-drop boundary conditions, and leads to a nonlinear multipoint boundary-value problem. Turbulent interchange, radial thermal conduction, and forced flow due to wire wraps or grids between channels are explicitly taken into account. Temperature distributions in the coolant, cladding, fuel, and duct wall and the size of the central void of the oxide fuel after thermal restructuring are computed. Also included are program-input description and format, and a sample problem reflecting these improvements.

A number of situations where it has been claimed that moderate radiation doses cause leukemia or other cancers are carefully reviewed. We look at cases in the United States, Great Britain, and the Soviet Union. Usually it can be demonstrated that there is an alternative, more probable, explanation for the effect seen. In several cases the authors of the papers have fallen into statistical traps. The most frequent is a posteriori selection of cohort boundaries in both space and time: a trap illustrated dramatically by Feynman. The next most common trap is to arbitrarily select one out of many ways of looking at the data, against which we were warned by Tippett. Several cohorts are compared with respect to the number of persons at risk, average dose, and the number of cancers expected. Of these, only the cohort of A-bomb survivors in Japan and the recently unclassified data on the very large occupational doses for early Soviet nuclear workers at Chelyabinsk provide evidence of clearly visible excess cancers.

Report issued by the Argonne National Laboratory discussing the Liquid Metal Fast Breeder Reactor Nuclear Safety Program. The work completed by the program between 1969 and 1970 is presented. This report includes tables, illustrations, and photographs.

Report issued by the Argonne National Laboratory over "the use of an electromagnetic field to control the laminar film condensation of a vapor whose liquid is electrically conducting" (p. 7). This report includes tables, and illustrations.

Suspected fission-product releases from 18 subassemblies between April 1977 and May 1978 are presented. Post-irradiation examinations pm 15 of the suspect subassemblies confirmed that all contained one or more breached elements. Except for two untagged subassemblies, xenon tagging was the primary method of identification, although other methods were used where appropriate. Methods to monitor and identify fission product sources are discussed. Problems encountered elements on plant availability were minimal during this reporting period. From all evidence, cladding breaching on elements in EBR-II continues to be a benign process.

Quarterly report on activities of Argonne National Laboratory's Nuclear Technical Programs, including a review of studies of the ability of backfill to inhibit groundwater flow in a nuclear waste repository.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Quarterly report of the Argonne National Laboratory Chemical Engineering Division regarding activities related to properties and handling of radioactive materials, operation of nuclear reactors, and other relevant research.

Directed Technologies, Inc. has previously submitted a detailed technical assessment and concept design for a mid-size, five-passenger fuel cell electric vehicle (FCEV), under contract to Argonne National Laboratory. As a supplement to that contract, DTI has reviewed the literature and conducted a preliminary evaluation of two energy carriers for the FCEV: hydrogen and methanol. This report compares the estimated fuel efficiency, cost of producing and delivering the fuel, and the resultant life cycle costs of the FCEV when fueled directly by hydrogen and when fueled by methanol with on-board reforming to produce the required hydrogen-rich gas for the fuel cell. This work will be supplemented and expanded under the Ford contract with the Department of Energy to develop the FCEV and its fuel infrastructure.

Improving Pollution Prevention and Waste Minimization Program (PP/WMIN) technologies, actions, and culture could be an important cost-cutting step for the US Department of Energy (DOE). Communicating ideas, concepts, process changes, and achievements is essential for the success of this program. The need to openly communicate ideas and concepts in a cost-effective manner is essential in an organization that has such diverse components as research and development, weapons production, and power generation. This approach is in contrast to the historic DOE culture developed within the cold war period in which compartmentalization, independence, and secrecy were stressed. DOE has now recognized that for any pollution prevention program to be successful, the many diverse elements of the organization must share information. Avenues for such information exchange are examined in this report.

This report is a compilation of Fast Breeder Reactor (FBR) resource documents prepared to provide the technical basis for the US contribution to the International Nuclear Fuel Cycle Evaluation. The eight separate parts deal with the alternative fast breeder reactor fuel cycles in terms of energy demand, resource base, technical potential and current status, safety, proliferation resistance, deployment, and nuclear safeguards. An Annex compares the cost of decommissioning light-water and fast breeder reactors. Separate abstracts are included for each of the parts.

Annual report of the Ion Replacement Electrorefining Program at Aronne National Laboratory describing their research and activities. There are three key accomplishments highlighted for the year: (1) identification of a suitable sodium(beta){double_prime}-alumina/molten salt electrolyte system that functions reproducibly at 723 K, (2) actual separation of dysprosium and lanthanum in experiments, and (3) the identification of a metal alloy, Li{sub x}Sb, as an alternative ion replacement electrode.

This report summarizes the work that has been performed to date at Argonne National Laboratory on the development of the TRUEX process, a solvent extraction process employing a bifunctional organophosphorous reagent in a PUREX process solverc (tributyl phosphate-normal paraffinic hydrocarbons). The purpose of this extraction process is to separate and concentrate transuranic (TRU) elements from nuclear waste.

Concurrently with the production of canned uranium slugs for pile operation there arises the problem of nondestructive testing so that no slug which may fail structurally during operation be placed in the pile. The ultimate goal of any such testing program is to devise nondestructive testing methods which will eliminate defective slugs. A secondary goal of the testing program is to learn as much as possible about the construction of the canned slug so that the mechanisms of failure can be understood. Radiography, an increasingly useful nondestructive test method, offered one possible way of investigating this area.

A technique for incorporating automatic transformations into processes such as the application of inference rules, subsumption, and demodulation provides a mechanism for improving search strategies for theorem proving problems arising from the field of program verification. The incorporation of automatic transformations into the inference process can alter the search space for a given problem, and is particularly useful for problems having broad rather than deep proofs. The technique can also be used to permit the generation of inferences that might otherwise be blocked and to build some commutativity or associativity into the unification process. Appropriate choice of transformations, and new literal clashing and unification algorithms for applying them, showed significant improvement on several real problems according to several distinct criteria.

Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).

From Review of Theory: " In practice, a very close approximation to the molecular orbitals can be obtained in this way. Recent calculations of this type, utilizing analysis and computer programs developed by the author, have resulted in the determination of the molecular orbitals for a large number of diatomic molecules in the form of Eq. (2). These functions, which are thought to be very close to the Hartree-Fock (i.e., the molecular orbitals demanded by theory) result, were used in the pictorial calculations presented in this report."

A set of experiments, based on the application of the Unsaturated Test method to the reaction of uranium dioxide with EJ-13 water, has been conducted over a period of 182.5 weeks. One half of the experiments have been terminated, while one half are still ongoing. Solutions that have dripped from uranium dioxide specimens have been analyzed for all experiments, while the reacted uranium dioxide surfaces have been examined for only the terminated experiments. A pulse of uranium release from the uranium dioxide solid, in conjunction with the formation of dehydrated schoepite on the surface of the uranium dioxide, was observed during the 39- to 96-week period. Thereafter, the uranium release decreased and a second set of secondary phases was observed. The latter phases incorporate cations from the EJ-13 water and include boltwoodite, uranophane, sklodowskite, compreignacite, and schoepite. The experiments are being continued to monitor for additional changes in solution composition and secondary phase formation, and have now reached the 319-week period.

The PTA-1 code for computing pressure transients in piping networks includes a computational model to treat the significant effect of plastic deformation of the piping on pulse propagation. Stanford Research Institute has completed an experimental program on the response of piping systems to internal pressure pulses which plastically deform portions of the piping. This report makes extensive comparisons between PTA-1 computations and these experimental results. The excellent agreement obtained for both pressure histories and strain histories for all the experiments indicates that the PTA-1 computational model for pipe plasticity effects is accurate. The computation-experiment comparisons also permit a number of observations and conclusions to be made on other aspects of computational modeling of pressure transients, particularly with respect to pulse propagation around elbows.