This manual is intended as a basis for plutonium-238 recovery costs and as a guide for removal of plutonium-bearing wastes from the gloveboxes to be safely and economically discarded. Waste materials contaminated with plutonium-238 are generated from in-house production, analytical, process development, recovery and receipts from off-site. The contaminated materials include paper, rags, alpha-box gloves, piping, valves, filters, etc. General categories for all types of plutonium waste have been established by the ERDA and are reflected in this manual. There are numerous processes used in plutonium recovery, such as dissolution, ultrasonic cleaning, ion exchange, etc. One or more of these processes are needed to extract the plutonium-238 from waste materials, purify it and convert it to an oxide acceptable for reuse. This manual is presented in two parts: Part I gives a breakdown and brief explanation of the direct costs for plutonium-238 I recovery, derived from budget data. Direct costs include direct labor (operating personnel), operational materials and supplies, health physics direct labor, calorimetry labor, analytical labor, and engineering direct labor (total costs for Method I). Budgeted costs for labor and material were used in the derivation of discard limits. The data presented is then used to calculate the cost …

This paper describes the Mound plutonium study. The objectives of the project were to evaluate the inventory of plutonium 238 in the environment at Mound, determine the source, and alleviate potential health hazards. Analysis of soils, water, vegetation, fishes, and runoff were performed.

Monsanto Research Corporation operates Mound Laboratory, a government-owned facility of the U.S. Energy Research and Development Administration, at Miamisburg, Ohio. Mound Laboratory is an integrated research, development, and production facility performing work in support of ERDA weapon and non-weapon programs with emphasis on explosive and nuclear technology. Mound Laboratory originated as a technical organization in 1943 when Monsanto Chemical Company was requested to accept responsibility for determining the chemical and metallurgical properties of polonium as a project of the Manhattan Engineering District. Work was carried on at Monsanto`s Central Research Department and several satellite units in the Dayton, Ohio area. Late in 1945, the Manhattan Engineering District determined that the research, development and production organization established by Monsanto at Dayton should become a permanent facility. A search for a suitable location in early 1946 led to the selection of a 180-acre tract adjacent to Miamisburg, about ten miles (16 km) south of Dayton.

Mound Laboratory, Miamisburg, Ohio is operated by Monsanto Research Corporation and is responsible to the Albuquerque Operations Office. It is an integrated production and laboratory facility which performs production and process development for weapons programs and conducts research and development for several other ERDA programs. Its missions are directed toward explosives and nuclear technologies. Total authorized plant and equipment is valued at $105.3 million. Gross operating funds for FY 1975 are estimated at $42.5 million. FY 1975 employment at midyear was 1,699. This paper provides an overview of the staff and technical qualifications, and technical capabilities of the Mound Laboratory.

This 1974 annual report presents a brief overview of work being performed in the following areas at the Mound Plant: explosive operations, nuclear operations, analytical developments, environmental control and waste management, computer programming, and supporting activities.

This correspondence provides a discussion of purported hazards of nuclear energy production and weapons research. The possibility of atmospheric burn and oceanic burn are discounted, and the cross sections of Nitrogen are investigated and the concentration of D[sub 2]O in the oceans are considered. In conclusion, extremely conservative calculations demonstrated that it is completely impossible for either the earth`s atmosphere or sea to sustain fusion reactions of either thermonuclear nuclear chain reaction type. And, in particular, such reactions cannot be triggered by the explosion of nuclear weapons, even those having unrealistically high yield and impractical high yield-to-weight.

This paper provides an evaluation and critical review of the possibilities for uranium isotope separation using matrix techniques.

The questions asked and answered include: Why was the program renamed from PNE (Peaceful Nuclear Explosives) to NEA? Why are storage cavities needed? Why can`t existing caves and mines be used? Isn`t a mined cavity safer for radioactive disposal? Why can`t one tolerate asymmetry between the US and USSR PNE capability? Why do we need PNE execution capability to support verification capability? Why shouldn`t the money go directly to verification? What is the priority of PNE research compared to other energy technology research? What is the US obligation under Article V of the NPT if it is determined that PNE`s are not worthwhile? What new information is available which shows that PNE`s will be politically acceptable? How much has been spent to develop PNE`s to date? What viable technology has resulted? The remainder of the paper discusses research programs being carried out on nuclear explosion technology and one technology that has resulted from the PNE program, namely, stimulation of oil and gas extraction.

This report is a bibliography from the International Aerospace Abstracts and the Scientific and Technical Aerospace Abstracts on remotely piloted vehicles. Most of the applications of these RPV`s are military in nature.

The microelectronics capability at Sandia Laboratories spans the complete range of component activity from initial design to final assembly into subsystems and systems. Highly reliable, radiation-tolerant devices and integrated circuits can be designed, fabricated, and incorporated into printed circuit assemblies or into thick- or thin-film hybrid microcircuits. Sandia has an experienced staff, exceptional facilities and aggressive on-going programs in all these areas. The authors can marshall a broad range of skills and capabilities to attack and solve problems in design, fabrication, assembly, or production. Key facilities, programs, and capabilities in the Sandia microelectronics effort are discussed in more detail in this booklet.

This paper is a reflection on the current understanding of the unprotected transient overpower (TOP) accident, in order to place it in perspective with regard to FFTF core energetics. The experimental data base is addressed, wtih particular emphasis on the E and H-series data, and its relevance to axial failure location and hydraulic fuel sweepout is considered. It is shown that the only way in which TOP could lead to a sizeable energy release is if either total plugging takes place or a plug at the radial center of the subassemblies propagates to the hex can walls prior to neutronics shutdown. (DLC)

This is the first of two significant assessments of the geological energy potential of the U.S. The second one is U.S.G.S. Circular 790. Systems analyzed include: Hydrothermal convection systems (with estimates of potential for many specific sites in the West), Igneous related systems (related to current or recent volcanism), Estimates of the conductive transport of heat in most areas of CONUS, Recovery of heat from molten igneous systems (magma), and Geopressured geothermal energy in the Gulf Coast area. The significance of this report is that it began to give policy makers a first handle on the quantities and qualities of geothermal energy in the ground in much of the U.S. Economics (costs and revenues) are not considered. (DJE - 2005)

The proposed Salton Sea Geothermal Power Pilot Plant Program comprises two phases. The objective of Phase 1 is to develop the technology for power generation from high-temperature, high-salinity geothermal brines existing in the Salton Sea known geothermal resources area. Phase 1 work will result in the following: (a) Completion of a preliminary design and cost estimate for a pilot geothermal brine utilization facility. (b) Design and construction of an Area Resource Test Facility (ARTF) in which developmental geothermal utilization concepts can be tested and evaluated. Program efforts will be divided into four sub-programs; Power Generation, Mineral Extraction, Reservoir Production, and the Area Resources Test Facility. The Power Generation Subprogram will include testing of scale and corrosion control methods, and critical power cycle components; power cycle selection based on an optimization of technical, environmental and economic analyses of candidate cycles; preliminary design of a pilot geothermal-electric generating station to be constructed in Phase 2 of this program. The Mineral Extraction Subprogram will involve the following: selection of an optimum mineral recovery process; recommendation of a brine clean-up process for well injection enhancement; engineering, construction and operation of mineral recovery and brine clean-up facilities; analysis of facility operating results from environmental, economical …

The Geothermal Steam Act and the implementing Regulations printed here governed most aspects of the leasing of Federal lands for geothermal exploration and development for many years. They are of great historical interest. Interesting details include: limits on leased acreage per person or firm, distinctions between competitive and noncompetitive leases, rules for bonus auctions, rents, and production royalties, diligence requirements, and distribution of royalties between the Government and the states. Note that most of what was laid out here prevailed until relatively large revisions in the omnibus Energy Bill of 2005. (DJE 2005)

This describes the main terms and systems covered in a comprehensive labor and material requirements model developed shortly after the U.S. energy crisis of 1973. For most of the 66 electricity production (conversion) technologies covered (e.g., coal, nuclear), quantitative values are shown for energy inputs and energy output. Geothermal flashed steam, 200 MWe complex, is system 64, and only output is shown for it. Values are shown for 25 energy transportation and transmission items. The culmination of the report is an application of the model to the President's Energy Program. While the values here are dated in details, reader can still get quick comparisons among technologies. Other reports from the model are likely in the OSTI collections. (DJE-2005)

To supply the heat input required by space-borne Vuilleumier refrigerators, a possible design for a reliable Pu-238 radioisotope heat source, based on state-of-the-art technology, is described. The isotope heat source would replace electrical heaters powered by solar panels and batteries, and would be adaptable to existing VM refrigerators without redesign. The heat source contains all necessary safety features, and also a simple thermal control system to permit refrigerator shut-down for indefinite duration. A system for thermal interfacing with the spacecraft, the booster, and ground support is also described. The isotope heaters are compared with solar-electric heaters for the same application, and found to result in very significant weight and size savings.

A bibliography of environmental research is presented which consists of items published between 1952 and mid-1975 by past and present staff members of the Ecosystems Dept., Battelle Pacific Northwest Laboratories. The material is arranged by alphabetical listing of author. Under each author, publications are listed chronologically by publication date in the categories of: journal articles, books, reports, and patents. No indexes are included. (LCL)

Progress is reported in a number of projects related to chemical research and technology, chemistry instrumentation, pilot plant development, and process chemistry and engineering.

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The critical dimensions of a sphere of an aqueous solution of 37-wt%-{sup 235}U-enriched uranyl fluoride and of several unreflected and water-reflected cylinders at a number of chemical concentrations were determined experimentally. The critical uranium concentration in the unreflected sphere was 51.93 g/liter. The neutron multiplication factor of the sphere was calculated by the DSN transport code in the S{sub 4} approximation to be 1.0100; the relative fission-rate distribution along a diameter, also calculated by DSN, compared favorably with measurements. The results from the cylinders, although less detailed and less accurate, can be generalized for nuclear criticality safety guidance. The dimensions of equivalent spheres, infinite cylinders, and infinite slabs were estimated for selected chemical concentrations by equating bucklings.

Waste supernate stored in Tank 11H was analyzed periodically from May 1973-August 1975 to determine the rate of nitrite ingrowth by radiolytic decomposition of nitrate. This waste was transferred to tank 33F in accordance with TA 2-892, Rev. 1, 'Use of Cracked Tank for Fresh High Level Waste,' during the week of November 10, 1975. This letter summarizes analytical and corrosion characterization which indicate that this transfer should not increase the risk of stress corrosion cracking in F Area non-stress-relieved tanks. An interpretation of the nitrite ingrowth data is presented and used as a basis for cokncluding that the crack in Tank 11H occurred early in 1974. The formation of nitrite in waste supernate was followed for 2 1/4 years during the last filling and storage cycle in 11H. The conversion of nitrate to nitrite in the 1 1/2 year period after filling was 4.9 x 10{sup -11} mol NO{sub 2}{sup -}/{ell} BTU of fission product heat. The energy released during the period was 1.15 x 10{sup 10} BTU with a corresponding increase in nitrite of 0.56 mol/{ell}. The crack that was first observed in Tank 11H in April 1974 probably made its final penetration through the wall in March …

Kinetics for grain boundary penetration and weight loss were determined for 304L stainless steel in Ti-gettered liquid Li. Empirical weight loss rate coefficient expressions were determined as function of both N content and temperature which predict the weight loss behavior of stainless steel for Li with high N content. Capillarity was eliminated as a possible driving force for grain boundary penetration of Fe by Li with the evidence of a grain boundary groove. Coupled ionic diffusion in a corrosion product surface film is suggested as the controlling mechanism for grain boundary grooving of Fe in N-contaminated liquid Li. Stress-enhanced grain boundary penetration showed that the penetration of stressed Fe is a function of t sup 1/3 rather than t sup 1/2, suggesting that primary creep of the Fe is continually breaking the protective corrosion product in the grain boundaries. A new purification procedure and systems were designed and constructed to achieve very low N contents in the liquid Li (less than 300 ppM N). A gas purification train, based on a molten Al bubbler for the removal of O and N, was designed and built, and vacuum melting of as-received Li and gettering are being initiated. Experiments designed to determine …

Yield and water relations in the Los Alamos supply wells were evaluated because of the increasing demand for water. Water-level declines were extrapolated for 10 yr, to 1983, on the basis of past records. On the basis of current pumpage, the extrapolations indicate that nonpumping water levels in individual wells will decline from 10 to 30 ft. Well characteristics were compiled to provide an individual history of each well, and recommendations for improving water production are presented. (auth)

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