The finite element method applied to neutron diffusion problems

Originally presented as the first author's thesis (Nucl. Eng.)--Massachusetts Institute of Technology Dept. of Nuclear Engineering, 1973Includes bibliographical references (pages 99-100

Finite element methods for space-time reactor analysis

"MIT-39-3-5."Also issued as a Sc. D. thesis by Chang Mu Kang in the Dept. of Nuclear Engineering, 1971Includes bibliographical references (leaves 147-150)AT(30-1) 390

The application of alternating-direction implicit methods to the space-dependent kinetics equations

Cover title"MIT-3903-3."Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1969Includes bibliographical references (leaves 54-55)Prepared under U.S. Atomic Energy Commission AT(30-1) 390

Nuclear power plant performance in the United States and the Federal Republic of Germany.

This report presents data comparing the performance of light water reactors in the United States and the Federal Republic of Germany (FRG). The comparisons are made for the years 1980-1983 and include 21 Westinghouse Pressurized Water Reactors (PWRs), 22 General Electric Boiling Water Reactors (BWRs) in the US; and 6 Kraftwerk Union (KWU) PWRs and 4 KWU BWRs in the FRG.Data on capacity losses are presented in a disaggregated form for scheduled outages, forced outages, and regulatory imposed outages. Further, within the scheduled and forced outages, the data is subdivided into losses associated with the nuclear island, the balance of plant, or other causes.The report also surveys a number of observations relating to the causes of discrepancies between the US and West Germany. These observations were obtained from interviews with executives and engineers in both nations, including people from vendors, utilities, regulators, and architect/engineers. These discussions are distilled into observations relating to national differences in the broad areas of economics and economic regulation, safety regulations, and technical and managerial differences

Finite difference techniques for the solution of the reactor kinetics equations

Also issued as a Sc. D. thesis in the Dept. of Nuclear Engineering, MIT,1969"MIT-3903-2."Bibliography: leaves 70-71AT(30-1)390

The finite element method for neutron diffusion problems in hexagonal geometry

Originally presented as the first author's thesis (Ph. D.), M.I.T. Dept. of Nuclear Engineering, 1975Includes bibliographical references (pages 163-164)Energy Research and Development Agency report AT(11-1)-226

Numerical solution of the two-dimensional time-dependent multigroup equations

Also issued as a Ph. D. thesis in the Dept. of Nuclear Engineering, MIT, 1969"MIT-3903-1."Includes bibliographical references (leaves 60-61)Contract AT(30-1)-390

Multi-group diffusion methods

"NYO-10, 206."Includes bibliographical references (page 71)AT(30-1)234

Solution of the space-dependent reactor kinetics equations in three dimensions

"August, 1971.""MIT-3903-4."Also issued as a Ph. D. thesis by the first author and supervised by the second author, MIT, Dept. of Nuclear Engineering, 1971Includes bibliographical references (pages 86-88)A general class of two-step alternating-direction semi-implicit methods is proposed for the approximate solution of the semi-discrete form of the space-dependent reactor kinetics equations. An exponential transformation of the semi-discrete equations is described which has been found to significantly reduce the truncation error when several alternating-direction semi-implicit methods are applied to the transformed equations. A subset of this class is shown to be a consistent approximation to the differential equations and to be numerically stable. Specific members of this subset are compared in one- and two-dimensional numerical experiments. An "optimum" method, termed the NSADE (Non-Symmetric Alternating-Direction Explicit) method is extended to three-dimensional geometries. Subsequent three-dimensional numerical experiments confirm the truncation error, accuracy, and stability properties of this method.U. S. Atomic Energy Commission contract AT (30-1) 390

The Reliability of Global and Hemispheric Surface Temperature Records

The purpose of this review article is to discuss the development and associated estimation of uncertainties in the global and hemispheric surface temperature records. The review begins by detailing the groups that produce surface temperature datasets. After discussing the reasons for similarities and differences between the various products, the main issues that must be addressed when deriving accurate estimates, particularly for hemispheric and global averages, are then considered. These issues are discussed in the order of their importance for temperature records at these spatial scales: biases in SST data, particularly before the 1940s; the exposure of land-based thermometers before the development of louvred screens in the late 19th century; and urbanization effects in some regions in recent decades. The homogeneity of land-based records is also discussed; however, at these large scales it is relatively unimportant. The article concludes by illustrating hemispheric and global temperature records from the four groups that produce series in near-real time