Quarterly report discussing fuel cell research and development work at Argonne National Laboratory (ANL). This report describes efforts directed toward (1) developing alternative concepts for components for molten carbonate fuel cells and (2) improving our understanding of component behavior.

When calculations of flux are done in less than three dimensions, bucklings are normally used to model leakages (flows) in the dimensions for which the flux is not calculated. If the net leakage for a given energy group is outward (positive), the buckling is positive, and buckling methods work well. However, if the new leakage for a given energy group is inward (negative), the buckling is negative and can lead to numerical instabilities (oscillations in the iterative flux calculation). This report discusses two equivalent non-buckling methods to model inward leakages. One method (the chi/sub g/ method) models these incoming neutrons by additional fission sources. The other method (the sigma/sub s/(1 --> g) method) models them by increased down-scatter sources. The derivation of the two methods is shown, and the flux spectra obtained by their use are compared with those obtained from two-dimensional (RZ) calculations.

This report describes a conjugate gradient preconditioning scheme for solving a certain system of equations which arises in the solution of a three dimensional partial differential equation. The problem involves solving systems of equations where the matrices are large, sparse, and non-symmetric.

A neutronic analysis has been made with respect to the ex-core neutron detector response during the TMI-2 incident. A series of transport theory calculations quantified the impact upon the detector count rate of various core and down-comer conditions. In particular, various combinations of coolant void content and spatial distributions were investigated to yield the resulting transmission of the photo-neutron source to the detector. The impact of a hypothetical distributed source within the down-comer region was also examined in order to simulate the potential effect of the release of neutron producing fission products into the coolant. These results are then offered as potential explanations for the anomalous behavior of the detector during the period of approx. 20 minutes through approx. 3 hours following the reactor scram.

The successful operation of D-T fusion reactors will depend on the development of safe and reliable tritium-containment and fuel-recycle systems. The tritium handling requirements for D-T reactors were analyzed. The reactor facility was then designed from the viewpoint of tritium management. Recovery scenarios after a tritium release were generated to show the relative importance of various scenarios. A fusion-reactor tritium facility was designed which would be appropriate for all types of plants from the Engineering Test Facility (ETF), the International Tokamak Reactor (INTOR), and the Fusion Engineering Device (FED) to the full-scale power plant epitomized by the STARFIRE design.

The general objective of the study is to perform a diversion analysis and an assessment of the available safeguards methods and systems for verifying inventory and flow of nuclear material in accessible and inaccessible areas of liquid-metal fast breeder reactor, LMFBR, systems. The study focuses primarily on the assembly-handling operations, assembly storage facilities, and reactor operations facilities relating to existing and/or near-term planned experimental, demonstration and prototypal reactor plants. The safeguards systems and methods presented are considered to be feasible for development and for implementation within the resource limitation of the IAEA and are considered to be consistent with the objectives, requirements, and constraints of the IAEA as outlined in the IAEA documents INFCIRC/153 and INFCIRC/66-Rev-2.

This report covers the processing and analysis of the fuel-bearing section (M-5138) of an irradiated experimental Light Water Breeder Reactor fuel rod, GRIP-II rod No. 79-453; this section has been designated the Validation Rod. Process steps included precision shearing of the rod into eight comminuted segments, dissolution of the segments, and chemical and radiometric analyses of the resulting solutions. The shearing and dissolution were carried out fully remotely in an existing pilot-scale facility installed in a shielded cell. Data are provided on physical parameters of the rod section and segments, uranium assays and isotopic abundances, and selected fission products. An error analysis of the individual measurements and analyses is included.

From introduction: In 1975 a project was begun to provide information on several aspects of coal hydrology in Ohio. The first phase was a reconnaissance of water-quality conditions in coal-mining regions. Phase one had two primary objectives; to document the occurrence of certain inorganic and organic constituents in waters of the coal-mining regions and to determine if the concentrations of those constituents were related to coal mining. The second phase of the project was a more detailed study of four basins sampled during the first phase.

Report documenting standard x-ray diffraction powder patterns for various compounds, intended to replace previous data or provide information for new substances. It describes the methods and, for each substance, outlines any previous data as well as information about the sample used and structural data, with a table of diffraction patterns.

Recorded laboratory analysis for samples of filtered spring, stream, and well water, and acidified stream and lake water from the Bakersfield quadrangle in California.

Recorded data taken from field samples of filtered spring, stream, and well water, and acidified stream and lake water from the Bakersfield quadrangle in California.

"Field and laboratory data are presented for 1780 sediment samples from the Bakersfield Quadrangle, California. The samples were collected by the Savannah River Laboratory; laboratory analysis and data reporting were performed by the uranium resource Evaluation Project at Oak Ridge Tennessee." (from Abstract)

"Field and laboratory data are presented for 1890 sediment samples from the Sacramento Quadrangle, California. The samples were collected by Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (from Abstract)

Recorded laboratory analysis for samples of filtered spring, stream, and well water, and acidified stream and lake water from the Sacramento quadrangle in California.

"Field and laboratory data are presented for 665 sediment samples from the San Luis Obispo Quadrangle, California. The samples were collected by the Savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee."

Recorded laboratory analysis for samples of filtered spring, stream, and well water, and acidified stream and lake water from the San Luis Obispo quadrangle in California.

Recorded data taken from field samples of filtered spring, stream, and well water, and acidified stream and lake water from the San Luis Obispo quadrangle in California.

Recorded data taken from field samples of filtered spring, stream, and well water, and acidified stream and lake water from the Sacramento quadrangle in California.

From abstract: "Guide for those who design, specify, use, and test military automatic test equipment containing sensors."

Recorded data taken from field samples of filtered spring, stream, and well water, and acidified stream and lake water from the Fresno quadrangle in California.

Recorded laboratory analysis for samples of filtered spring, stream, and well water, and acidified stream and lake water from the Fresno quadrangle in California.

"Field and laboratory data are presented for 1038 sediment samples from the Fresno Quadrangle, California. The Samples were collected by Savannah River Laboratory; Laboratory analysis and data reporting were performed by the Uranium Resource Evaluation Project at Oak Ridge, Tennessee." (Abstract)

Recorded data taken from field samples of filtered spring, stream, and well water, and acidified stream and lake water from the Goldfield quadrangle in California and Nevada.

"Field and laboratory data are presented for 790 sediment samples from the Goldfield Quadrangle, California; Nevada. The samples were collected by savannah River Laboratory; laboratory analysis and data reporting were performed by the Uranium Resource evaluation Project at Oak Ridge, Tennessee." (from Abstract)