The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume II, the SIMWEST operation manual, describes the usage of the SIMWEST program, the design of the library components, and a number of simple example simulations intended to familiarize the user with the program's operation. Volume II also contains a listing of each SIMWEST library subroutine.

A system of computer codes has been developed to statistically reduce Peach Bottom fuel test element metrology data and to compare the material strains and fuel rod-fuel hole gaps computed from these data with HTGR design code predictions. The codes included in this system are STAT, STRAIN, GAPS, and DRWDIM. STAT statistically evaluates test element metrology data yielding fuel rod, fuel body, and sleeve irradiation-induced strains; fuel rod anisotropy; and additional data characterizing each analyzed fuel element. STRAIN compares test element fuel rod and fuel body irradiation-induced strains computed from metrology data with the corresponding design code predictions. GAPS compares test element fuel rod, fuel hole heat transfer gaps computed from metrology data with the corresponding design code predictions. DRWDIM plots the measured and predicted gaps and strains. Although specifically developed to expedite the analysis of Peach Bottom fuel test elements, this system can be applied, without extensive modification, to the analysis of Fort St. Vrain or other HTGR-type fuel test elements.

An analysis of the parameters involved in the sintering of lead powders under vacuum has been made. Sintering was accomplished at temperatures between 250/sup 0/ and 280/sup 0/C. Evaluation of surface area reduction data results in values of the mechanism exponent N between 5.3 and 6.7. Lack of shrinkage and the low vapor pressure of lead at the experimental temperatures lead to the conclusion that surface diffusion is the rate-controlling sintering mechanism. However, comparison of the experimentally measured activation energy, 170 kJ/mol (40.7 Kcal/mol), to that reported in the literature for surface self-diffusion of lead showed a significant discrepancy. Effects of pore isolation and surface oxide layers are proposed as possible explanations for this discrepancy as well as the deviation in the N values from those obtained theoretically. An attempt to isolate the effect of the oxide layer was made by sintering lead in a hydrogen atmosphere. Under these conditions, sintering is accompanied by shrinkage, thus indicating the presence of bulk-transport process. A mechanism exponent corresponding to viscous flow sintering was obtained. Furthermore, the calculated activation energy for this process was in good agreement with that reported for creep in lead.

The effort developed a comprehensive computer program for the modeling of wind energy/storage systems utilizing any combination of five types of storage (pumped hydro, battery, thermal, flywheel and pneumatic). An acronym for the program is SIMWEST (Simulation Model for Wind Energy Storage). The level of detail of SIMWEST is consistent with a role of evaluating the economic feasibility as well as the general performance of wind energy systems. The software package consists of two basic programs and a library of system, environmental, and load components. Volume I gives a brief overview of the SIMWEST program and describes the two NASA defined simulation studies.

From abstract: "This report presents recommendations for proper investigation, design, and construction of retaining dikes to aid in ensuring that these dikes will be constructed with a minimum of problems and will serve their project requirements."

Results from the previously conducted Semiscale Mod-1 ECC injection test series were analyzed. Testing in the LOFT counterpart test series was essentially completed, and the steam generator tube rupture test series was begun. Two tests in the alternate ECC injection test series were conducted which included injection of emergency core coolant into the upper plenum through use of the low pressure injection system. The Loss-of-Fluid Test Program successfully completed nonnuclear Loss-of-Coolant Experiment L1-4. A nuclear test, GC 2-3, in the Power Burst Facility Reactor was performed to evaluate the power oscillation method of determining gap conductance and to determine the effects of initial gap size, fill gas composition, and fuel density on the thermal performance of a light water reactor fuel rod. Additional test results were obtained relative to the behavior of irradiated fuel rods during a fast power increase and during a high power film boiling transient. Fuel model development and verification activities continued for the steady state and transient Fuel Rod Analysis Program, FRAP-S and FRAP-T. A computer code known as RELAP4/MOD7 is being developed to provide best-estimate modeling for reflood during a postulated loss-of-coolant accident (LOCA). A prediction of the fourth test in the boiling water reactor …

This report summarizes collected data of soils from 45 sites meant to characterize the operational environments in dredged material containment areas in nine Corps of Engineer districts in the United States so that performance of low-ground-pressure vehicles operating in these areas could be predicted.

This Final Safety Analysis Report (FSAR) supplements the Preliminary Safety Analysis Report (PSAR), dated January 18, 1974, for Building 332, Increment III of the Plutonium Materials Engineering Facility located at the Lawrence Livermore Laboratory (LLL). The FSAR, in conjunction with the PSAR, shows that the completed increment provides facilities for safely conducting the operations as described. These documents satisfy the requirements of ERDA Manual Appendix 6101, Annex C, dated April 8, 1971. The format and content of this FSAR complies with the basic requirements of the letter of request from ERDA San to LLL, dated March 10, 1972. Included as appendices in support of th FSAR are the Building 332 Operational Safety Procedure and the LLL Disaster Control Plan.

This quarterly report is the fifth in a series intended to provide information on research and engineering activities being performed to improve the processing of irradiated reactor fuels, the production of plutonium, and the management of resultant chemical wastes.

The report discusses and evaluates the adequacy of buyer specifications for snubbers. Technical specifications for snubbers (hydraulic and mechanical) were studied in detail in an effort to define the ''fundamental needs'' of the industry with respect to characteristics of snubbers during operation. In the course of this study, it was determined that there is insufficient consensus among users to make such a definition. Authorities in the fields of structural dynamics, structural systems design, and snubber design were also consulted for additional information. Information from these sources is incorporated to identify the fundamental areas of concern, areas where consensus is lacking, and problems to be resolved in order to establish meaningful standards for this equipment.

This report discusses the effectiveness of the EBR-II fuel-element-rupture-detector (FERD) system which detects delayed-neutron-emitting fission products. It is demonstrated that FERD provides no reactor or public protection for loss-of-flow or transient-overpower fault events that affect the whole core; such protection is provided by other systems.

This edition dated August 26, 1977, is Revision C of the Integrated Test Vehicle, Program Plan, Phase II - Deliverable Item 2-7-1. The original edition was issued on May 27, 1977. Corrections were made and issued as Proposed Modifications for Integrated Test Vehicle, Program Plan, dated July 8, 1977. For the purpose of documenting changes, the July 8, 1977, version is caled Revision A. The edition dated August 5, 1977, is called Revision B. Each paragraph in this edition is marked to indicate technical changes from previous editions.

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A simple subroutine based on the Tektronix Plot-10/Advanced Graphing II package to be used with a Tektronix CRT terminal is presented. It is specifically designed for the needs of a physicist, but contains enough options to allow for a wider use. 1 figure.

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This report identifies barriers to shortening nuclear power plant construction schedules and recommends research efforts that should minimize or eliminate the identified barriers. The identified barriers include: (1) design and construction interfacing problems; (2) problems relating to the selection and use of permanent materials and construction methods; (3) construction coordination and communication problems; and (4) problems associated with manpower availability and productivity;

SPEAKEASY does not have within it FORTRAN-type functions. A function like sin(x) is defined as a table of values at specified points and is held in the computer as an array. Because of this, the differential equation to be solved is defined only at certain points. This problem must be confronted; the algorithms and the code employing them do quite well at meeting the requirements for acceptable solution. The algorithms used are described, and step size, order, and errors are discussed. Several examples are given, along with a listing of subroutine SPKODE. (RWR)

A general description is provided of electrical transmission systems as an aid in determining their environmental impacts. Alternating current, direct current, overhead systems, underground systems, and water crossings are treated. The cost, performance, reliability, safety, and environmental impact of these systems are compared.

This report presents results from an investigation on the creep-fatigue and cyclic-deformation of Type 16-8-2 (16% Cr-8% Ni-2% Mo) stainless steel weld metal. Tests were conducted in air at 593 degrees C and a strain rate of 0.004 s⁻¹. Comparisons with data for Type 316 stainless steel base metal indicated that the weld metal has significantly longer fatigue lives for several tension hold-time tests. This is attributed to the fine duplex microstructure of the weld metal that inhibits the growth rate of cracks. Additional studies on the cyclic deformation behavior of the weld metal indicate that the material is strain-history dependent; therefore a unique stress-strain curve does not exist. Monotonic tension tests after cyclic straining result in a different stress-strain curve than obtained from companion fatigue tests at various completely reversed constant strain ranges. A comparison of the fracture morphology and creep-rupture specimens indicates that differences resulting from these tests can be attributed to different failure mechanisms.

This Safety Analysis Report for Packaging demonstrates that model UC-609 shipping package can safely transport tritium in any of its forms. The package and its contents are described. The package when subjected to the transport conditions specified in the Code of Federal Regulations, Title 10, Part 71 is evaluated. Finally, compliance with these regulations is discussed.

The design of a solar heating and hot water system for the New Castle Redevelopment Authority's single-family dwelling located at New Castle, Pennsylvania is described. Documentation submitted by the contractor for Government review of plans, specifications, cost trade studies and verification status for approval to commit the system to fabrication is presented. Also included are system integration drawings, major subsystems drawings, and architect's specifications and plans.

Documents relevant to the development and implementation of the California energy insulation standards for new residential buildings were evaluated and a survey was conducted to determine problems encountered in the implementation, enforcement, and design aspects of the standards. The impact of the standards on enforcement agencies, designers, builders and developers, manufacturers and suppliers, consumers, and the building process in general is summarized. The impact on construction costs and energy savings varies considerably because of the wide variation in prior insulation practices and climatic conditions in California. The report concludes with a series of recommendations covering all levels of government and the building process. (MCW)

This publication is the eleventh supplement to, and revision of, ANL-7411. It contains additional abstracts and revisions to some earlier abstracts and other pages. Sections of the complete document ANL-7411 are as follows: preface, history and acknowledgements, abstract format, recommended program package contents, program classification guide and thesaurus, and the abstract collection. (RWR)

The broad subject of the meeting is the overall ERDA TRU waste management program, although the discussions also cover performance criteria for the Waste Isolation Pilot Plant and their implications for the overall TRU program. Separate abstracts were prepared for all ten presentations. (DLC)