A technique for accelerating the aging process of thermally activated batteries that use iron disulfide was developed. In this approach, storage at 130/sup 0/C for one week was assumed equivalent to a shelf life of five years. Some of the batteries stored at 130/sup 0/C were discharged to test for functionality changes, and others were disassembled and carefully analyzed for evidence of deleterious reactions. Some functionality anomalies were observed. The only deleterious reaction observed was that of Li(Si) reacting with water vapor. 3 figures, 6 tables.

On May 22, 1980, a symposium was held at Brookhaven to celebrate the 20th birthday of the AGS, to recall its beginnings, and to review major discoveries that have been made with its beams. The talks at the symposium are recorded in this volume.

The removal of CO/sub 2/ from air was investigated by using a continuous-agitated-slurry carbonation reactor containing either barium hydroxide (Ba(OH)/sub 2/) or calcium hydroxide (Ca(OH)/sub 2/). Such a process would be applied to scrub /sup 14/CO/sub 2/ from stack gases at nuclear-fuel reprocessing plants. Decontamination factors were characterized for reactor conditions which could alter hydrodynamic behavior. An attempt was made to characterize reactor performance with models assuming both plug flow and various degrees of backmixing in the gas phase. The Ba(OH)/sub 2/ slurry enabled increased conversion, but apparently the process was controlled under some conditions by phenomena differing from those observed for carbonation by Ca(OH)/sub 2/. Overall reaction mechanisms are postulated.

By introducing a similarity variable r/..sqrt..t a quasi-analytical method can be used to calculate the flow induced by the injection of cold water into a hot water or boiling geothermal reservoir. The results obtained are compared with those produced by the reservoir simulator SHAFT79 and show good agreement.

A method was developed to extract and then analyze gas trapped in thermally aged 1E34 detonators. This gas was extracted into an evacuated volume and injected into a gas chromatograph for separation and quantitative analysis. To effect this gas extraction, a device was designed for puncturing the detonator cup and capturing the effused gas. Limited testing of five detonators in this device shows amounts of gas ranging from about 0.5 X 10 {sup -7} to 12 X 10 {sup - 7} moles.

The progress is reported in the following sections: analytical methodology, mass and emission spectrometry, technical support, bio-organic analysis, nuclear and radiochemical analysis, and quality assurance. (DLC)

Environmental monitoring results continue to demonstrate that, except for penetrating radiation, environmental radiological impact due to SLAC operation is not distinguishable from natural environmental sources. During 1979, the maximum measured neutron dose near the site boundary was not distinguishable from the cosmic ray neutron background. There have been no measurable increases in radioactivity in ground water attributable to SLAC operations since 1966. Because of major new construction, well water samples were not collected and analyzed during 1979. Construction activities have also temporarily placed our sampling stations for the sanitary and storm sewers out of service. They will be reestablished as soon as construction activities permit (mid 1980). Airborne radioactivity released from SLAC continues to make only a negligible environmental impact, and results in a site boundary annual dose of less than 0.3 mrem; this represents less than 0.3% of the annual dose from the natural radiation environment, and about 0.06% of the technical standard.

International meetings under the BEFAST program and under INFCE Working Group No. 6 during 1978 and 1979 continue to indicate that no cases of fuel cladding degradation have developed on pool-stored fuel from water reactors. A section from a spent fuel rack stand, exposed for 1.5 y in the Yankee Rowe (PWR) pool had 0.001- to 0.003-in.-deep (25- to 75-..mu..m) intergranular corrosion in weld heat-affected zones but no evidence of stress corrosion cracking. A section of a 304 stainless steel spent fuel storage rack exposed 6.67 y in the Point Beach reactor (PWR) spent fuel pool showed no significant corrosion. A section of 304 stainless steel 8-in.-dia pipe from the Three Mile Island No. 1 (PWR) spent fuel pool heat exchanger plumbing developed a through-wall crack. The crack was intergranular, initiating from the inside surface in a weld heat-affected zone. The zone where the crack occurred was severely sensitized during field welding. The Kraftwerk Union (Erlangen, GFR) disassembled a stainless-steel fuel-handling machine that operated for 12 y in a PWR (boric acid) spent fuel pool. There was no evidence of deterioration, and the fuel-handling machine was reassembled for further use. A spent fuel pool at a Swedish PWR was decontaminated. …

As a service element within the Federal Wind Energy Program, the Wind Characteristics Program Element (WCPE) is established to provide the appropriate wind characteristics information to those involved in: the design and evaluation of wind energy conversion systems (WECS); energy program planning; selecting sites for WECS installation; and the operation of WECS. To effectively produce the information needed in these four categories, the WCPE, for which the Pacific Northwest Laboratory (PNL) has the responsibility for management and technical assistance, has been divided into four technical program areas. During this reporting period PNL was also assigned the management responsibility for the data collection at the US Department of Energy's (DOE's) candidate sites, as well as the task of providing technical assistance to DOE evaluation and site selection panels for new candidate sites.

Air spaces in a deep geologic repository for nuclear high level waste will have an important effect on the long-term performance of the waste package. The important temperature effects of an annular air gap surrounding a high level waste canister are determined through 3-D numerical modeling. Air gap properties and parameters specifically analyzed and presented are the air gap size, surfaces emissivity, presence of a sleeve, and initial thermal power generation rate; particular emphasis was placed on determining the effect of these variables have on the canister surface temperature. Finally a discussion based on modeling results is presented which specifically relates the results to NRC regulatory considerations.

Appendix to report "Test PCM-5 Fuel Rod Materials Behavior" presenting pretest physical characteristics of the Power-Cooling-Mismatch Test Series PCM-5 fuel rod components.

Report presenting details of Test-PCM-5 fuel rod axial power profiles as determined by two methods: gamma scanning of the fuel bundle flux wires and radiochemical burnup analysis of fuel samples from Rods 205-1, -2, -3, -5, -7, -8, and -9. (p. B-2)

Appendix presenting postest bundle and individual fuel rod photographs for report "Test PCM-5 Fuel Rod Materials Behavior."

Report presenting rod-to-rod spacing measurements and individual rod diameter measurements for fuel rods used in the Power-Cooling-Mismatch Test Series PCM-5.

Report presenting preparation of the Power-Cooling-Mismatch Test Series PCM-5 fuel rods and fuel rod sections for metallographic examination and the metallographic examination results from Rods 205-1, -2, -3, -4, -5, -6, and -8.

Report presenting cladding axial and circumferential temperature estimates, fuel rod radial temperature estimates, and the techniques used to estimate the cladding and fuel temperatures for Power-Cooling-Mismatch Test Series PCM-5.

Report presenting microprobe examination results of fuel Rods 205-1, 205-2, and 205-8 for test Power-Cooling-Mismatch Test Series PCM-5.

Report presenting fuel rod particle sizes and size distributions as determined for the two failed Test PCM-5 fuel rods.

Report presenting scanning electron microscopy (SEM) examinations used to analyze one cladding fracture surface of Rod 205-4 for Power-Cooling-Mismatch Test Series PCM-5.

The public exposure from spent fuel shipment is very low. In view of this low exposure and the perfect safety record for spent fuel shipment, existing systems can be considered satisfactory. On the other hand, occupational exposure reduction merits consideration and technology improvement to decrease dose should concentrate on this exposure. Practices that affect the age of spent fuel in shipment and the number of times the fuel must be shipped prior to disposal have the largest impact. A policy to encourage a 5-year spent fuel cooling period prior to shipment coupled with appropriate cask redesign to accommodate larger loads would be consistent with ALARA and economic principles. And finally, bypassing high population density areas will not in general reduce shipment dose.

This paper describes the results of digital image analysis and techniques applied to acoustic sounder data and topographic relief in the Geyser's region. The two dimensional fast Fourier transform (2DFFT) represents the spacial variability of a photographic image. The spacial variability of topography in complex terrain can be represented in this way and insight into degree of complexity and dominating spacial wavelengths can be gained. This was performed for a 16 km square digitized topographic map of the Geyser's region with 63.5 m resolution. It was also of interest to compare facsimile recordings of acoustic sounder data to optical turbulence measurements.

Nondestructive gamma-ray and neutron techniques were used to characterize the irradiation exposures of irradiated fuel assemblies. Techniques for the rapid measurement of the axial-activity profiles of fuel assemblies have been developed using ion chambers and Be(..gamma..,n) detectors. Detailed measurements using high-resolution gamma-ray spectrometry and passive neutron techniques were correlated with operator-declared values of cooling times and burnup.

The four phases of ongoing work at SERI that examines many unresolved questions regarding the purpose, solar applicability, economics, and energy modeling of industral parks are presented. The first phase involved site visits to approximately 300 parks in 12 major metropolitan areas of 9 states. Phase 2 entails an analysis of four parks selected from those parks surveyed. Phase 3 narrows the focus to two parks to be examined for detailed technical and engineering analysis. Phase 4 incorporates all of the work of the earlier phases with economic criteria to produce an energy allocation model describing energy delivery and consumption within the park.

The purpose of this handbook is to assist in understanding the various procedures and requirements necessary for the development of geothermal energy in the State of Arizona. It contains the names of key persons and agencies who are directly or indirectly involved in the institutional process. A detailed assessment of all agencies and the role they play in geothermal energy development is provided. The handbook is divided into four sections: State and Local rules and regulations, the Federal rules and regulations, references, and a technical bibliography. (MHR)