This revised publication updates a previous report (ANL-7291) initially published in 1965, entitled Radiation Safety Technician Training Course which was intended to complement on-the-job monitoring training for Health Physics Technicians. Sections include basic information concerning atomic structure and other useful physical quantities, natural radioactivity, the properties of alpha, beta, gamma, x rays and neutrons, and the concepts and units of radiation dosimetry (including SI units).

The EBWR loading requires a total of 888 plates. It is anticipated that approximately 1000 plates will have to be produced to obtain the number of acceptable plates required for the loading. To the end of this quarter, 568 cladding billet cores acceptable with respect to chemical composition and physical soundness had been cast; this number represents 78% of the total number of cores cast. Approximately 75% of the Zircaloy-II stock required has been rolled, and about 55% of the cladding components required have been finished. The anticipated number of 495 cladding billets required for the thin (0.210") natural and enriched plates have been assembled, welded, sealed, and jacketed in steel. A total of 310 cladding billets have been rolled to fuel plates; of this number, 142 have been completely finished, and the remaining 168 are in the finish processing stages. The stability of the equipment for measuring the clad thickness of EBWR fuel plates has been improved by placing the phototube and the anthracene scintillator crystals in an insulated box with a temperature regulation of the order of 0.1°F.

FX2-TH is a two-dimensional, time-dependent nuclear reactor kinetics program with thermal and hydraulic feedback. The neutronics model used is multi-group neutron diffusion theory. The following geometry options are available: x, r, x-y, r-z, theta-r, and triangular. FX2-TH contains two basic thermal and hydraulic models: a simple adiabatic fuel temperature calculation, and a more detailed model consisting of an explicit representation of a fuel pin, gap, clad, and coolant. FX2-TH allows feedback effects from both fuel temperature (Doppler) and coolant temperature (density) changes. FX2-TH will calculate a consistent set of steady state conditions by iterating between the neutronics and thermal-hydraulics until convergence is reached. The time-dependent calculation is performed by the use of the improved quasistatic method. A disk editing capability is available. FX2-TH is operational on IBM system 360 or 370 computers and on the CDC 7600.

The COMMIX-LAR/P computer program is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-lA to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a keg model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the program to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The internal aspects of the COMMIX-LAR/P program are presented, covering descriptions of subprograms, variables, and files. This document provides a description of each subroutine and variable, showing linkage among these and their relation to the equations and variables presented in Volume 1.

The mathematical development and numerical solution of the finite-difference equations are summarized. The report provides a guide for user application and details the programming structure of DIF3D. Guidelines are included for implementing the DIF3D export package on several large scale computers. Optimized iteration methods for the solution of large-scale fast-reactor finite-difference diffusion theory calculations are presented, along with their theoretical basis. The computational and data management considerations that went into their formulation are discussed. The methods utilized include a variant of the Chebyshev acceleration technique applied to the outer fission source iterations and an optimized block successive over-relaxation method for the within-group iterations. A nodal solution option intended for analysis of LMFBR designs in two- and three-dimensional hexagonal geometries is incorporated in the DIF3D package and is documented in a companion report, ANL-83-1.

The solution of large sparse systems of linear equations is at the heart of many algorithms in scientific computing. The SLES package is a set of easy-to-use yet powerful and extensible routines for solving large sparse linear systems. The design of the package allows new techniques to be used in existing applications without any source code changes in the applications.

JAKEF is a compiler that accepts as data a single or double precision FORTRAN subroutine program defining an objective function F(x) or a vector function f(x) and produces as output a single or double precision FORTRAN program defining the gradient of F(x) or the Jacobian of f(x).

Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including applied chemistry, separation science and technology, and high-level waste and repository interactions.

A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the elimination of frequently observed segmented inclusions at the seal pin interfaces.

Most casting defects occur during initial pouring and therefore the design of the running system, which guides the metal from the ladle into the mold, is crucial. Traditionally, the running system and mold filling are designed by trial and error, which is tedious, time consuming, and expensive. The uncertainties that remain can be overcome by a computer simulation that demonstrates the actual process of mold filling and subsequent solidification. Computer simulation of various processes has become more and more common in recent years. The cost-effectiveness of making flawless castings has made the foundry worker more aware of the process of mold filling, identification of hot spots, etc. The macroscopic Casting Process Simulator (CaPS) software combines heat transfer and fluid flow aspects and can describe a variety of solidification aspects, including mold filling. CaPS is a two-dimensional time-dependent computer code involving a finite-volume formulation for the mass, momentum. and energy equations. CaPS has the following characteristics. CaPS uses the PATRAN geometric modeling package for constructing the geometry, generating a neutral file consisting of a list of named components, and post-processing of the simulation results; building the geometry independently of the mesh is a time-saving procedure. A structured mesh generator of structured …

This project was conducted to evaluate the practicality of using laboratory groundwater stream experiments to model a hydraulic breach of a nuclear waste repository located deep in a bedded salt environment. A test plan is included in this report that gives details of the apparatus, rocks, solutions, and analyses to be used in a groundwater stream experiment. Preliminary experiments revealed the essential impermeability of halite; only a small concentration of water (about 75 ppm) moved in halite by diffusion, with a coefficient of 2.0 x 10⁻⁷/ cm sq./s. From work completed in this program, groundwater stream experiments appear to be a practical method of establishing the chemical interactions that would occur in a breached repository in bedded salt.

Progress report of the Argonne National Laboratory's Nuclear Technology Programs involving R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management.

Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including investigations in applied physical chemistry, separation science and technology, and waste management.

Report documenting the creation of a computer program (written in FORTRAN and MACRO) to assist researchers in writing technical documents that include formulas and graphics. It includes operating instructions for using the program and example documents.

Highlights of the Chemical Technology (CMT) Division's activities during 1989 are presented. In this period, CMT conducted research and development in the following areas: (1) electrochemical technology, including high-performance batteries (mainly lithium/iron sulfide and sodium/metal chloride), aqueous batteries (lead-acid and nickel/iron), and advanced fuel cells with molten carbonate and solid oxide electrolytes; (2) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized-bed combustion; (3) method, for recovery of energy from municipal waste and techniques for treatment of hazardous organic waste; (4) nuclear technology related to a process for separating and recovering transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor (the Integral Fast Reactor), and waste management; and (5) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.

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.

Annual report of the Argonne National Laboratory Radiological and Environmental Research Division regarding activities related to molecular physics and chemistry. This report discusses a study on the physical properties and the chemical reactions of atmospheric constituents, with emphasis on the role of pollutants arising from the use of fossil fuels. Special effort is being placed on understanding nucleation phenomena through the study of the molecular properties of gas phase clusters.

This report describes ALICE, which uses an arbitrary Lagrangian-Eulerian method to analyze the response of the contaminant vessel and other solid media inside a reactor contaminant.

Highlights of the Chemical Technology (CMT) Division's activities during 1988 are presented. In this period, CMT conducted research and development in the following areas: (1) high-performance batteries (mainly lithium-alloy/metal sulfide, sodium/metal chloride, and sodium/sulfur); (2) aqueous batteries (lead-acid, nickel/iron, etc.); (3) advanced fuel cells with molten carbonate or solid oxide electrolytes; (4) coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized bed combustion; (5) methods for recovery of energy from municipal waste and techniques for treatment of hazardous chemical waste; (6) nuclear technology related to a process for separating and recovering. transuranic elements from nuclear waste and for producing 99Mo from low-enriched uranium targets, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor, and waste management; and (7) physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.

Progress report of the Argonne National Laboratory's Nuclear Technology Programs, including R&D in three areas: applied physical chemistry, separation science and technology, and nuclear waste management.

Annual report of activities of the Argonne National Laboratory Physics Division, including research at ATLAS, medium-energy nuclear physics and weak interactions, theoretical nuclear physics, and atomic and molecular physics research.

Highlights of the Chemical Technology (CMT) Division's activities during 1985 are presented. In this period, CMT conducted research and development in areas that include advanced batteries--mainly lithium-alloy/metal sulfide and sodium/sulfur, advanced fuel cells with molten carbonate or solid oxide electrolytes, corrosion-protective coatings for high-strength steel, coal utilization, including the heat and seed recovery technology for coal-fired magnetohydrodynamics plants and the technology for fluidized-bed combustion, methodologies for recovery of energy from municipal waste nuclear technology related to waste management, the recovery processes for discharged fuel and the uranium blanket in a sodium-cooled fast reactor, and proof of breeding in a light water breeder reactor, and physical chemistry of selected materials in environments simulating those of fission and fusion energy systems.

The COMMIX-1AR/P computer code is designed for analyzing the steady-state and transient aspects of single-phase fluid flow and heat transfer in three spatial dimensions. This version is an extension of the modeling in COMMIX-1A to include multiple fluids in physically separate regions of the computational domain, modeling descriptions for pumps, radiation heat transfer between surfaces of the solids which are embedded in or surround the fluid, a k-(epsilon) model for fluid turbulence, and improved numerical techniques. The porous-medium formulation in COMMIX allows the code to be applied to a wide range of problems involving both simple and complex geometrical arrangements. The input preparation and execution procedures are presented for the COMMIX-1AR/P program and several post processor programs which produce graphical displays of the calculated results. This document provides a step-by-step of how to use the program, including an input guide and a sample problem.

Report of the activities of the physics division at Argonne including the successful completion of Argonne Tandem-Linac Accelerator System.