Sorbent injection is a low capital cost, low operating cost approach to SO{sub 2} control targeted primarily at older boilers for which conventional fuel gas desulfurization is not economically viable. Duct injection is one variation of this concept in which the sorbent, either a dry powder or a slurry, is injected into the cooler regions of the boiler, generally downstream of the air heaters. The attractiveness of duct injection is tied to the fact that it avoids much of the boiler heat transfer equipment and thus has minimal impact of boiler performance. Both capital and operating cost are low. This program has as its objectives three performance related issues to address: (1) experimentally identify limits on sorbent performance. (2) identify and test sorbent performance enhancement strategies. (3) develop a compute model of the duct injection process. Two major tasks are described: a laboratory-scale global experiment and development of process model. Both are aimed at understanding and quantifying the rate-limiting processes which control SO{sub 2} capture by lime slurry during boiler duct injection. 29 refs., 35 figs., 4 tabs.

This report covers the project progress of grant DE-FG02-86ER60422 for the period March 1, 1990--October 1, 1990. The research program includes three tasks: General Circulation Models (GCM) intercomparison and improvement, climate data-model statistics, and China project science coordination. This work has been performed in collaboration with our subcontractor, Dr. Wei-Chyung Wang, SUNY/Albany. 8 refs.

The chemical and physical properties of {sup 218}Po immediately following its formation from {sup 222}Rn decay are important in determining its behavior in indoor atmospheres and plays a major part in determining its potential health effects. In 88% of the decays, a singly charged positive ion of {sup 218}Po is obtained at the end of its recoil path. The neutralization rates for Po-218 by the small ion recombination, electron transfer or electron scavenging mechanisms were previously reported. We have measured the small ion recombination rate in high purity gases to determine the negative small ion production rate as a function of the ionization potential of the gas. Our previous studies have also shown that radiolysis of water vapor by the recoiling Po ion produces high local concentrations of hydroxyl ({center dot}OH) radicals. These radicals can lead to oxidation of reactive trace gases and the neutral polonium molecule can become incorporated in ultrafine particles formed by the nucleation of low vapor pressure compounds produced by this radical oxidation process. The hydroxyl radical production rate and the production of particles are currently being studied. 12 refs., 1 fig.

The SIGMA-PI ({Sigma}{Pi}) method as implemented in the SIGPI computer code, is designed to accurately and efficiently evaluate the probability of Boolean expressions in disjunctive normal form given the base event probabilities. The method is not limited to problems in which base event probabilities are small, nor to Boolean expressions that exclude the compliments of base events, nor to problems in which base events are independent. The feasibility of implementing the {Sigma}{Pi} method on a personal computer has been evaluated, and a version of the SIGPI code capable of quantifying simple Boolean expressions with independent base events on the personal computer has been developed. Tasks required for a fully functional personal computer version of SIGPI have been identified together with enhancements that could be implemented to improve the utility and efficiency of the code.

Radioactive waste stored in underground tanks at the West Valley Demonstration Project is being processed into low-level waste and solidified in cement. High-level waste also stored underground will be vitrified and solidified into canistered glass logs. To move the waste from where it resides at the Waste Tank Farm to the Vitrification Facility requires equipment to prepare the storage tanks for low-level and high-level waste processing, equipment to mobilize and mix the radioactive sludge into a homogeneous slurry, and equipment to transfer the slurry for vitrification. The design of the Sludge Mobilization System has incorporated the necessary components to effect the preparation and transfer of waste in five operational phases. The first phase of the Sludge Mobilization System, which began in 1987, prepared the waste tanks to process radioactive liquid for delivery to the Cement Solidification System and to support the mobilization equipment. The second phase, beginning in 1991, will wash the sludge that remains after the liquid supernatant is decanted to prepare it for mobilization operations. The third phase will combine the contents of various waste tanks into one tank. The fourth phase will resuspend and mix the contents of the high-level waste tank. The fifth and final phase …

We have made good progress in formulating our procedures for assembly of prototype sensor parts to alleviate problems of oxidation/reduction of components and possibly deleterious interactions of component materials. We have been working exclusively with the simplest form of prototype, i.e. without an incorporated heater. This has been to save assembly time and materials and to simplify the system of the components while we have dealt with overriding, non-heater'' assembly issues. It is anticipated future inclusion of the heater will introduce some new problems to be overcome, but we do not think these will be overwhelming.

This paper discusses the following topics: antiproton nucleus interactions; strangeness production in heavy ion collisions; search for a J{sup PC} exotic hybrid meson; the SMC experiment; pion production in {rvec n}p scattering; spin transfer measurements for {rvec n}p elastic scattering; pion production in {rvec n}{rvec p} scattering; radiative muon capture (RMC) on hydrogen; radiative decays of low-lying hyperons; photoproduction of jets in nuclei; cylindrical multiplicity detector; MWPC detectors and electronics; lead glass array; cylindrical wire chamber; beam calorimeter; shower counter; and muon veto hodoscope.

The Vitrification Facility (VF) at the West Valley Demonstration Project was designed to convert stored radioactive waste into a stable glass for disposal in a federal repository. The Functional and Checkout Testing of Systems (FACTS) program was conducted from 1984 to 1989. During this time new equipment and processes were developed, installed, and implemented. Thirty-seven FACTS tests were conducted, and approximately 150,000 kg of glass were made by using nonradioactive materials to simulate the radioactive waste. By contrast, the planned radioactive operation is expected to produce approximately 500,000 kg of glass. The FACTS program demonstrated the effectiveness of equipment and procedures in the vitrification system, and the ability of the VF to produce quality glass on schedule. FACTS testing also provided data to validate the WVNS waste glass qualification method and verify that the product glass would meet federal repository acceptance requirements. The system was built and performed to standards which would have enabled it to be used in radioactive service. As a result, much of the VF tested, such as the civil construction, feed mixing and holding vessels, and the off-gas scrubber, will be converted for radioactive operation. The melter was still in good condition after being at temperature …

This report discusses the nuclear structure of the following isotopes as a result of radioactive decays: neutron-deficient iridium isotopes; neutron-deficient platinum isotopes; neutron-deficient gold isotopes; neutron-deficient mercury isotopes; neutron-deficient thallium isotopes; neutron-deficient lead isotopes; neutron-deficient promethium isotopes; and neutron-deficient samarium isotopes.