The verification and adjustment of plant models for decay heat removal analysis using a mix of engineering judgment and formal techniques from control theory are discussed. The formal techniques facilitate dealing with typical test data which are noisy, redundant and do not measure all of the plant model state variables directly. Two pretest examples are presented.

Exposure to noise, H{sub 2}S, NH/sub 3/, hazardous chemicals and wastes, and heat are the major occupational health hazards associated with geothermal energy development - from drilling to power production. Exposures to these agents, although not unique to geothermal energy development, occur in situations peculiar to the industry. Reports show that occupational illnesses associated with geothermal energy development are increasing, while the corresponding rates from all power production are decreasing. Most of those related to geothermal energy result from the H{sub 2}S-abatement systems used in response to environmental pollution regulations.

A study of depository recharge and repressurization has been reviewed. Specific consideration has been given to the validity of two initial assumptions in that study. The first was a decision to ignore lateral flow and end effects into the depository. The second was a decision to ignore thermal effects. The review has been made with particular concern to assessing the sufficiency of the Golder model for estimation of worst-case (minimum) recharge-repressurization time (RRT) in a bedded salt depository. It has been concluded that several errors by Golder may have little net effect on this worst case scenario. Combination of lateral flow and thermal effects may, however, reduce the value of the Golder model for estimation of minimum RRT in a bedded salt facility. Several subjects for further model development are suggested, though the availability of data to support such models is not addressed.

Lawrence Livermore Laboratory (LLL) is conducting research on the seismic risk of nuclear power plants through the Seismic Safety Margins Research Program (SSMRP). Phase I of the SSMRP will include a study of an existing plant and site. Results are presented of a study of existing and planned nuclear power plants in the United States. Selection criteria were developed and a recommendation for a specific plant for the SSMRP Phase I effort is given. Power plant characteristics including types of nuclear steam supply steam, containment structure, electric power capacity, geographic location, site seismicity, and foundation soil properties were evaluated.

A diametral extensometer was developed and employed during temperature ramp tests with the Fuel Cladding Transient Tester (FCTT). Plastic strain measurements were performed using unirradiated 20% cold-worked AISI 316 stainless steel tubing ramped at 5.6 and 111/sup 0/C/s with internal pressures from 3.4 to 93.1 MPa. Results demonstrated that plastic deformation can occur at stresses well below the conventional 0.2% yield strength and that most deformation in such tests occurs in the final 50/sup 0/C before failure. Postirradiation tests were performed on fuel pin cladding irradiated to 5.8 x 10/sup 22/ n/cm (E > 0.1 MeV) with irradiation temperatures to 540/sup 0/C. The tests showed that, for test pressures of 17.2 MPa or less, the stress-strain behavior was unchanged from unirradiated material behavior although the strains at failure were greatly decreased.

The physical properties of brittle materials are of interest because of the rapidly expanding use of these material in high-pressure and shock wave techology, e.g., geophysics and explosive compaction as well as military applications. These materials are characterized by unusually high sonic velocities, have large dynamic impedances and exhibit large dynamic yield strengths.

This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program.

Instrumentation was designed for monitoring the state of charge of sealed lead--acid cells during discharge. This monitor utilizes the cell voltage during discharge, compensating for variations in load current and temperature. The discharge voltage is converted to a linear function of state of charge by a nonlinear amplifier. Statistics are given for the uncertainty in the monitor. Below 80% state of charge the monitor is accurate to better than +-5% state of charge at all currents in the C to C/10 range. 9 figures, 12 tables.

A study of the nonlinear saturation by mode coupling of the dissipative trapped-ion mode is presented in which both radial and poloidal variations are considered. The saturation mechanism consists of the nonlinear coupling via E x B convection of energy from linearly unstable modes to stable modes. Stabilization is provided at short poloidal wavelengths by Landau damping from trapped and circulating ions, at short radial wavelengths by effects associated with the finite ion banana excursions and at long wavelengths by ion collisions. A one-dimensional, nonlinear partial differential equation for the electrostatic potential derived in earlier work is extended to two dimensions and to third order in amplitude. Included systematically are kinetic effects, e.g., Landau damping and its spatial dependence due to magnetic shear. The stability and accessibility of equilibria are considered in detail for cases far from as well as close to marginal stability. In the first case three-wave interactions are found to be important when the spectrum of unstable modes is sufficiently narrow. In the latter case, it is found that for a single unstable mode, a four-wave interaction can provide the dominant saturation mechanism. Cross-field transport is calculated, and the scaling of results is considered for tokamak parameters.

The impact of the advances in the miniaturization of electronic components is related. The standardization program at LLL is reviewed; its principles should find application elsewhere. A small computer users library maintains master software tapes, documentation, educational materials, and catalogs. Other aspects of the program include software licensing agreements, the LSI-11 bulletin, EE bulletin, users meetings, stores stock and documentation, publications, educational facilities, hardware designs, memory programming center, simulators, and application assistance. 6 figures. (RWR)

References for the commonly cited technical papers in the area of computer protection are given. Great care is taken to exclude papers with no technical content or merit. For the purposes of this bibliography, computer protection is broadly defined to encompass all facets of the protection problem. The papers cover, but are not limited to, the topics of protection features in operating systems (e.g., MULTICS and HYDRA), hardware implementations of protection facilities (e.g., Honeywell 6180, System 250, BCC 5000, B6500), data base protection controls, confinement and protection models. Since computer protection is related to many other areas in computer science and electrical engineering, a bibliography of related areas is included after the protection bibliography. These sections also include articles of general interest in the named areas which are not necessarily related to protection.

Several models have been suggested to describe the volume behavior of porous materials under hydrostatic loading. The model presented here accounts for variations in both porosity and the amount of fluid contained within that porosity. The model also attempts to predict the one-dimensional strain loading pressure-volume relationship and the stress difference-confining pressure curve. Only the simplest assumptions were used for the development of this model. These assumptions are discussed and the predictions for Mt. Helen tuff are compared to experimental data.

It is proposed to study the direct production of electron pairs produced when a high energy proton interacts with the Coulomb field of a nucleus. This process occurs at fourth order in quantum electrodynamics. This phenomena, called trident production when the incident particle is an electron, is characterized by a single incident primary track and three emerging tracks. Accelerator experiments on direct pair production by protons have not been previously reported, due to the small cross-sections at energies less than 100 GeV. However, at an energy of 100 GeV the cross-section for the direct creation of electron pairs by protons in emulsion is about 10{sup -25}cm{sup 2}.

None

This report presents details of the activities of Douglas United Nuclear at the Hanford site during the month of July 1971.