Recent highlights in CP violation phenomena, are reviewed. B-factory results imply that, CP-violation phase in the CKM matrix is the dominant contributor to the observed CP violation in K and B-physics. Deviations from the predictions of the CKM-paradigm due to beyond the Standard Model CP-odd phase are likely to be a small perturbation. Therefore, large data sample of clean B's will be needed. Precise determination of the unitarity triangle, along with time dependent CP in penguin dominated hadronic and radiative modes are discussed. Null tests in B, K and top-physics and separate determination of the K-unitarity triangle are also emphasized.

This paper describes the approach of dealing with an historic legacy of pharmaceutical manufacturing operations, which arose as a result of the temporary cessation of sea disposal in 1983. The result of that cessation was an accumulation of 1,000 reinforced concrete lined steel drums containing intermediate level nuclear waste of mixed chemical and physical form. Included are the steps taken which established a policy, the resulting strategy and the unique and innovative means by which the plan was implemented. The objective was to reduce the financial liability of the waste contained within the drums by removing those portions that had already decayed, segregating the waste in terms of non disposable and disposable isotopes, size reduction and long-term storage of the residues in a retrievable waste form. As part of this process the Company established a UK strategy which would ensure that the Company was self sufficient in radioactive waste handling storage facilities until the provision of a national facility, currently predicted to be approximately 2040.

The authors report the observation of a narrow state decaying into J/{psi}{pi}{sup +}{pi}{sup -} and produced in 220 pb{sup -1} of {bar p}p collisions at {radical}s = 1.96 TeV in the CDF II experiment. They observe 730 {+-} 90 decays. The mass is measured to be 3871.3 {+-} 0.7(stat) {+-} 0.4(syst) MeV/c{sup 2}, with an observed width consistent with the detector resolution. This is in agreement with the recent observation by the Belle Collaboration of the X(3872) meson.

Division, Dow Chemical U.S.A., for shipping unirradiated fissile material in solid form. Components consist of a 30-gal steel drum, Celotex insulation, and stainless steel containment vessel(s) of 10-in. dia. A simple venting system prevents rtupture of the outer drum in the event of accidental fire. Approved material limits include 5 kg of plutonium or 11 kg of enriched uranium. Thermal decay energy is normally limited to 20 W. Results of extensive tests show the container will function effectively when exposed to all environment and accident conditions as required. The containment vessel temperature rise will not exceed 140 deg F during the thermal test. Internal heating of 20 W will cause an additional temperature rise of 80 deg F. (auth)

A remote measurement system has been constructed for in situ gamma and beta isotopic characterization of highly radioactive nuclear material in hostile environments. A small collimated, planar CdZnTe detector is used for gamma-ray spectroscopy. Spectral resolution of 2% full width at half maximum at 662 kiloelectronvolts has been obtained remotely using rise time compensation and limited pulse shape discrimination, Isotopc measurement of high-energy beta emitters was accomplished with a ruggedized, deeply depleted, surface barrier silicon dictator. The primary function of the remote nuclear screening system is to provide fast qualitative and quantitative isotopic assessment of high-level radioactive material.

Interference lithography is an emerging, technology that provides a means for achieving high resolution over large exposure areas (approximately 1 m{sup 2}) with virtually unlimited depth of field. One- and two-dimensional arrays of deep submicron structures can be created using near i-line wavelengths and standard resist processing. In this paper, we report on recent advances in the development of this technology, focusing, in particular, on how exposure latitude and resist profile scale with interference period We present structure width vs dose curves for periods ranging from 200 nm to 1 um, demonstrating that deep submicron structures can be generated with exposure latitudes exceeding 30%. Our experimental results are compared to simulations based on PROLITIV2.

Certain radioisotopes can penetrate concrete and contaminate the concrete well below the surface. The challenge is to determine the extent and magnitude of the contamination problem in real-time. The concrete profiling technology, TRUPROSM in conjunction with portable radiometric instrumentation produces a profile of radiological or chemical contamination through the material being studied. The data quality, quantity, and representativeness may be used to produce an activity profile from the hot spot surface into the material being sampled. This activity profile may then be expanded to ultimately characterize the facility and expedite waste segregation and facility closure at a reduced cost and risk. Performing a volumetric concrete or metal characterization safer and faster (without lab intervention) is the objective of this characterization technology. This way of determining contamination can save considerable time and money. Currently, concrete core bores are shipped to certified laboratories where the concrete residue is run through a battery of tests to determine the contaminants. The existing core boring operation volatilizes or washes out some of the contaminants (like tritium) and oftentimes cross-contaminates the area around the core bore site. The volatilization of the contaminants can lead to airborne problems in the immediate vicinity of the core bore. Cross-contamination …

This paper describes the commercial application of an innovative plasma mass separator called the Archimedes Filter to a pre-treatment plant that can be integrated into the U.S. Department of Energy (DOE) Hanford and Savannah River Sites to significantly enhance the treatment of radioactive high-level waste. The output of the Archimedes Filter is completely compatible with existing waste immobilization processes such as vitrification and requires no new waste form to be developed. A full-geometric-scale Demonstration Filter Unit (DEMO) has been constructed and is undergoing initial testing at the Archimedes Technology Group Development Facilities in San Diego. Some of the technology and engineering development is being performed by other organizations in collaboration with Archimedes. The Commissariat a l'Energie Atomique (CEA) is developing the plasma calcination technology and all of the associated systems for AFP feed preparation. Two Russian institutes are involved in the development of the ICP torch and injector system. The Remote System Group (UT-Battelle) at ORNL is developing the remote maintenance system for the filter units. Conceptual design of the Archimedes Filter Plant (AFP) is being developed concurrently with the DEMO testing program. The AFP mission is to significantly reduce the cost and accelerate the rate of vitrification of high-level …

This project focused on advancing radio-frequency (RF) lamination technology closer to commercial implementation, in order to reduce the energy intensity of glass lamination by up to 90%. Lamination comprises a wide range of products including autoglass, architectural safety and innovative design glass, transparent armor (e.g. bullet proof glass), smart glass, mirrors, and encapsulation of photovoltaics. Lamination is also the fastest growing segment of glass manufacturing, with photovoltaics, architectural needs, and an anticipated transition to laminated side windows in vehicles. The state-of-the-art for glass lamination is to use autoclaves, which apply heat and uniform gas pressure to bond the laminates over the course of 1 to 18 hours. Laminates consist of layers of glass or other materials bonded with vinyl or urethane interlayers. In autoclaving, significant heat energy is lost heating the chamber, pressurized air, glass racks, and the glass. In RF lamination, the heat is generated directly in the vinyl interlayer, causing it to heat and melt quickly, in just 1 to 10 minutes, without significantly heating the glass or the equipment. The main purpose of this project was to provide evidence that low energy, rapid RF lamination quality met the same standards as conventionally autoclaved windows. The development of …

This project focused on advancing radio-frequency (RF) lamination technology closer to commercial implementation, in order to reduce the energy intensity of glass lamination by up to 90%. Lamination comprises a wide range of products including autoglass, architectural safety and innovative design glass, transparent armor (e.g. bullet proof glass), smart glass, mirrors, and encapsulation of photovoltaics. Lamination is also the fastest growing segment of glass manufacturing, with photovoltaics, architectural needs, and an anticipated transition to laminated side windows in vehicles. The state-of-the-art for glass lamination is to use autoclaves, which apply heat and uniform gas pressure to bond the laminates over the course of 1 to 18 hours. Laminates consist of layers of glass or other materials bonded with vinyl or urethane interlayers. In autoclaving, significant heat energy is lost heating the chamber, pressurized air, glass racks, and the glass. In RF lamination, the heat is generated directly in the vinyl interlayer, causing it to heat and melt quickly, in just 1 to 10 minutes, without significantly heating the glass or the equipment. The main purpose of this project was to provide evidence that low energy, rapid RF lamination quality met the same standards as conventionally autoclaved windows. The development of …

As facility demolition and remediation continued at the DOE Ashtabula Environmental Management Project (AEMP), a DOE closure site located in Ashtabula, OH, the quantity of mixed waste increased by approximately twenty-fold from the original Site Treatment Plan estimates to over 567 m3 (20,000 cubic feet). Also, a greater variety of low-level mixed waste (MW) was identified that was suitable for alternate debris treatment like macroencapsulation (MACRO) instead of traditional shredding, stabilization, and solidification to improve the overall safety and cost-effectiveness. Macroencapsulation is required for lead and authorized for hazardous debris under the alternate debris treatment standards per 40 CFR 268.45. Several polymer encapsulation processes were being explored, developed, and deployed in the mid-1990's by various groups including the DOE Mixed Waste Focus Area, DOE EM-50 Office of Science and Technology, Brookhaven National Laboratory, DOE Macro Working Group, DOE-Albuquerque Mixed Waste/Mobile Treatment Unit, and Envirocare of Utah, Inc. As a result, technically-proven macroencapsulation and microencapsulation processes using extruded polyethylene beads were verified as being technically acceptable for waste treatment to RCRA standards. The AEMP had a variety of waste forms where technically-proven systems were needed to perform on-site treatment of challenging mixed wastes (MW) from production operations (i.e. HEPA filters, barium …

Both the Knolls Atomic Power Laboratory (KAPL) in Schenectady, NY and the Kesselring Site Operations (KSO) facility near Ballston Spa, NY are required to estimate the effects of hypothetical emissions of radiological material from their respective facilities by the US Environmental Protection Agency (EPA), which regulates these facilities. An atmospheric dispersion model known as CAP88, which was developed and approved by the EPA for such purposes, is used by KAPL and KSO to meet this requirement. CAP88 calculations over a given time period are based on statistical data on the meteorological conditions for that period. Both KAPL and KSO have on-site meteorological towers which take atmospheric measurements at a frequency ideal for EPA regulatory model input. However, an independent analysis and processing of the meteorological data from each tower is required to derive a data set appropriate for use in the CAP88 model. The National Atmospheric Release Advisory Center (NARAC) was contracted by KAPL to process the on-site data for the calendar year 2011. The purpose of this document is to: (1) summarize the procedures used in the preparation/analysis of the 2011 meteorological data; and (2) document adherence of these procedures to the guidance set forth in 'Meteorological Monitoring Guidance …

The analytic cell was mainly used for process control analysis of the reprocessing process and for the measurement of fuel burn up ratio in JAERI's Reprocessing Test Facility (JRTF). The analytic cell was a heavy shielded one and equipped with a conveyor. The cell was alpha and beta(gamma)contaminated. For dismantling of analytic cells, it is very important to establish a method to remove the heavy shield safely and reduce the exposure. At first, a green house was set up to prevent the spread out of contamination, and next, the analytic cell was dismantled. Depending on the contamination condition, the workers wore protective suits such as air ventilated-suits for prevention of internal exposure and vinyl chloride aprons, lead aprons in order to reduce external exposure. From the work carried out, various data such as needed manpower for the activities, the collective dose of workers by external exposure, the amount of radioactive wastes and the relation between the weight of the shield and its dismantling efficiency were obtained and input for the database. The method of dismantling and the experience with the dismantling of the analytic cell in the JRTF, carried out during 2001 and 2002, are described in this paper.

The necessity to develop the submarine fleet in Russia required constructing a special training base for the training of submarine crews. To this purpose two prototypes of nuclear power units, close analogous to those fitting out nuclear submarines were constructed and commissioned in the sixties on the Navy training centre's base located in Paldiski (Pakri peninsula, Estonia). In 1994, nuclear fuel was discharged from the reactors and transported to Russia while the reactors themselves were prepared for prolonged storage, prior to transfer of the Paldiski facilities to the ownership of the Estonian Republic. The Paldiski facilities are currently being dismantled with the exception of two sarcophagi made of concrete that are housing the two reactor compartments. The question of the future management of both sarcophagi is a key-issue in the cleaning up of the whole Paldiski site. Actually, three basic questions should answered: when should dismantling operations occur, how this should be done, and what could be the corresponding cost. Within the context of enlargement of the European Union, the Commission services (first Directorate-General for Environment and then Directorate-General for Enlargement) decided to support Estonia to respond to these three questions through a study contract that was awarded in 1999 …

The purpose of this design calculation is to estimate radiation doses received by personnel in the Remediation Facility performing operations to receive, prepare, open, repair, recover, disposition, and correct off-normal and non-standard conditions with casks, canisters, spent nuclear fuel (SNF) assemblies, and waste packages (WP). The specific scope of work contained in this calculation covers both collective doses and individual worker group doses on an annual basis, and includes the contributions due to external and internal radiation. The results of this calculation will be used to support the design of the Remediation Facility and provide occupational dose estimates for the License Application.

The purpose of this design calculation is to estimate radiation doses received by personnel working in the subsurface facility of the repository performing emplacement, maintenance, and retrieval operations under normal conditions. The results of this calculation will be used to support the design of the subsurface facilities and provide occupational dose estimates for the License Application.

The goals of this project are to investigate (1) the kinetics and stabilities of engineered cytochrome P450 (P450) small alkane hydroxylases and their evolutionary intermediates, (2) the structural basis for catalytic proficiency on small alkanes of these engineered P450s, and (3) the changes in redox control resulting from protein engineering. To reach these goals, we have established new methods for determining the kinetics and stabilities of multicomponent P450s such as CYP153A6. Using these, we were able to determine that CYP153A6 is proficient for hydroxylation of alkanes as small as ethane, an activity that has never been observed previously in any natural P450. To elucidate the structures of the engineered P450s, we obtained x-ray diffraction data for two variants in the P450PMO (propane monooxygenase) lineage and a preliminary structure for the most evolved variant. This structure shows changes in the substrate binding regions of the enzyme and a reduction in active site volume that are consistent with the observed changes in substrate specificity from fatty acids in the native enzyme to small alkanes in P450PMO. We also constructed semi-rational designed libraries mutating only residues in the enzyme active site that in one round of mutagenesis and screening produced variants that achieved …

For the conditioning of spent resins contaminated with radionuclides, such as: 137Cs, 134Cs, 60Co, 58Co, 57Co, 54Mn, etc., techniques of direct immobilization in cement, bitumen and organic polymers have been tested. The selected process was the bituminization using industrial bitumen, I 60-70, made in Romania, which had very good characteristics. The paper presents stages of the research project, technical conditions for the process and advantages of the bituminization of spent resins.

This paper describes the management of alpha waste that cannot be stored in surface repositories under current French regulations. The aim of the paper is to provide an overview of COGEMA's Integrated Waste Management Strategy. The topics discussed include primary waste minimization, from facility design to operating feedback; primary waste management by the plant operator, including waste characterization; waste treatment options that led to building waste treatment industrial facilities for plutonium decontamination, compaction and cement solidification; and optimization of industrial tools, which is strongly influenced by safety and financial considerations.

Normal butylamine compounds are studied as salt-free wash reagents for degraded solvent used in PUREX process in spent fuel reprocessing. The solvent wash tests were carried out with two types of butylamine compounds, n-butylamine oxalate and n-butylamine bicarbonate, by counter-current mode using a small size mixer-settler composed of two 4-stage wash steps. Di-n-butyl phosphoric acid (HDBP), the main degradation product from TBP, was removed from real degraded solvent with decontamination factor of 2.5 {approx} 7.9. The study on electrolytic decomposition of butylamine compounds was also conducted for waste treatment.

Technologies were investigated to determine viable processes for removing mercury from the calciner (NWCF) offgas system at the Idaho National Engineering and Environmental Laboratory. Technologies for gas phase and aqueous phase treatment were evaluated. The technologies determined are intended to meet EPA Maximum Achievable Control Technology (MACT) requirements under the Clean Air Act and Resource Conservation and Recovery Act (RCRA). Currently, mercury accumulation in the calciner off-gas scrubbing system is transferred to the tank farm. These transfers lead to accumulation in the liquid heels of the tanks. The principal objective for aqueous phase mercury removal is heel mercury reduction. The system presents a challenge to traditional methods because of the presence of nitrogen oxides in the gas phase and high nitric acid in the aqueous scrubbing solution. Many old and new technologies were evaluated including sorbents and absorption in the gas phase and ion exchange, membranes/sorption, galvanic methods, and UV reduction in the aqueous phase. Process modifications and feed pre-treatment were also evaluated. Various properties of mercury and its compounds were summarized and speciation was predicted based on thermodynamics. Three systems (process modification, NOxidizer combustor, and electrochemical aqueous phase treatment) and additional technology testing were recommended.

Activities of the Hanford Engineering Development Laboratory are presented. A brief description of FFTF and some highlights of reactor operations are reviewed. The sodium technology work at HEDL is summarized by discussing several facets of the program and their tie-ins to breeder reactor development.

During the past years a new cutting technology, the CAMX-process-family (Contact-Arc-Metal-X [X is for Cutting, Grinding and Drilling]) was developed at the Institute of Materials Science in Hanover. These are electro-thermal underwater separation processes for metallic structures. The CAMX technology covers the Contact-Arc-Metal- Cutting (CAMC) with a sword-like cutting electrode, the Contact-Arc-Metal-Grinding (CAMG) with a rotating electrode and the Contact-Arc-Metal-Drilling (CAMD) with a wrap mechanism to fix and carry the workpiece. There are no limitations of CAMC concerning the capability of cutting complicated structures of workpieces. Undercuts and cavities in the workpiece do not affect the CAMC. The CAMG is a separation process for straight cuts with a very high cutting speed. The CAMD is a technology to drill holes or pocket holes of any geometry. With the integrated wrap mechanism it is possible to fix and carry workpieces, which are not to handle with conventional mechanisms.

Pressures are mounting for a regime to verify the dismantlement of US and Russian warheads, as well as a system of international control over the weapons` fissile materials to assure irreversibility. There are at least four motivating factors for these measures: (1) as the United States and Russia lower their numbers of nuclear weapons, each side seeks assurance that the warheads are actually being dismantled; (2) by accounting for the fissile materials and placing them under effective controls, the potential for smuggling and theft is reduced; (3) a fissile materials cutoff is being discussed at the Conference on Disarmament in Geneva; verification of a US-Russian cutoff, as well as substantial reductions in fissile materials stockpiles, are seen as integral to the cutoff; (4) calls for total nuclear disarmament have greatly increased; dismantlement verification and international control of fissile materials are widely viewed as requisite steps toward this goal. There are many questions to be answered before the United States can agree to a warhead verification regime and international control over excess fissile materials, let alone total nuclear disarmament. Two of the most important are: What are the prospects for effective verification? and How much fissile material can be declared as …