Nonisothermal hydrologic transport experimental plan

International Nuclear Information System (INIS)

Rasmussen, T.C.; Evans, D.D.

1992-09-01

A field heater experimental plan is presented for investigating hydrologic transport processes in unsaturated fractured rock related to the disposal of high-level radioactive waste (HLW) in an underground repository. The experimental plan provides a methodology for obtaining data required for evaluating conceptual and computer models related to HLW isolation in an environment where significant heat energy is produced. Coupled-process models are currently limited by the lack of validation data appropriate for field scales that incorporate relevant transport processes. Presented in this document is a discussion of previous nonisothermal experiments. Processes expected to dominate heat-driven liquid, vapor, gas, and solute flow during the experiment are explained, and the conceptual model for nonisothermal flow and transport in unsaturated, fractured rock is described. Of particular concern is the ability to confirm the hypothesized conceptual model specifically, the establishment of higher water saturation zones within the host rock around the heat source, and the establishment of countercurrent flow conditions within the host rock near the heat source. Field experimental plans are presented using the Apache Leap Tuff Site to illustrate the implementation of the proposed methodology. Both small-scale preliminary experiments and a long-term experiment are described

Inspection and test planning

International Nuclear Information System (INIS)

Miller, T.

1980-01-01

Purpose of Quality Plan - arrangement of all necessary tests or inspections as far as possible filted to certain components or systems. Subject of Quality Plan - precise determination of tests or inspections and - according to the actual safety significance - the certificates to be done. Disposition of Quality Plan - accommodation of tests to the actual state of fabrication. Application of Quality Plan - to any component or system that is regarded. Supervision of Employment - by authorized personnel of manufacturer, customer or authority providing exact employment of quality plan. Overservance of Instructions - certificates given by authorized personnel. (orig./RW)

Experimental Plan: 300 Area Treatability Test: In Situ Treatment of the Vadose Zone and Smear Zone Uranium Contamination by Polyphosphate Infiltration

International Nuclear Information System (INIS)

Wellman, Dawn M.; Pierce, Eric M.; Oostrom, Mart; Fruchter, Jonathan S.

2007-01-01

The overall objectives of the treatability test is to evaluate and optimize polyphosphate remediation technology for infiltration either from ground surface, or some depth of excavation, providing direct stabilization of uranium within the deep vadose and capillary fringe above the 300 Area aquifer. Expected result from this experimental plan is a data package that includes: (1) quantification of the retardation of polyphosphate, (2) the rate of degradation and the retardation of degradation products as a function of water content, (3) an understanding of the mechanism of autunite formation via the reaction of solid phase calcite-bound uranium and aqueous polyphosphate remediation technology, (4) an understanding of the transformation mechanism, identity of secondary phases, and the kinetics of the reaction between uranyl-carbonate and silicate minerals with the polyphosphate remedy under solubility-limiting conditions, (5) quantification of the extent and rate of uranium released and immobilized based on the infiltration rate of the polyphosphate remedy and the effect of and periodic wet-dry cycling on the efficacy of polyphosphate remediation for uranium in the vadose zone and capillary fringe, and (6) quantification of reliable equilibrium solubility values for autunite under hydraulically unsaturated conditions allowing accurate prediction of the long-term stability of autunite. Moreover, results of intermediate scale testing will quantify the transport of polyphosphate and degradation products, and yield degradation rates, at a scale that is bridging the gap between the small-scale UFA studies and the field scale. These results will be used to test and verify a site-specific, variable saturation, reactive transport model and to aid in the design of a pilot-scale field test of this technology. In particular, the infiltration approach and monitoring strategy of the pilot test would be primarily based on results from intermediate-scale testing. Results from this

The Space Station Photovoltaic Panels Plasma Interaction Test Program: Test plan and results

Science.gov (United States)

Nahra, Henry K.; Felder, Marian C.; Sater, Bernard L.; Staskus, John V.

1989-01-01

The Plasma Interaction Test performed on two space station solar array panels is addressed. This includes a discussion of the test requirements, test plan, experimental set-up, and test results. It was found that parasitic current collection was insignificant (0.3 percent of the solar array delivered power). The measured arcing threshold ranged from -210 to -457 V with respect to the plasma potential. Furthermore, the dynamic response of the panels showed the panel time constant to range between 1 and 5 microsec, and the panel capacitance to be between .01 and .02 microF.

The Space Station photovoltaic panels plasma interaction test program - Test plan and results

Science.gov (United States)

Nahra, Henry K.; Felder, Marian C.; Sater, Bernard L.; Staskus, John V.

1990-01-01

The plasma Interaction Test performed on two space station solar array panels is addressed. This includes a discussion of the test requirements, test plan, experimental set-up, and test results. It was found that parasitic current collection was insignificant (0.3 percent of the solar array delivered power). The measured arcing threshold ranged from -210 to -457 V with respect to the plasma potential. Furthermore, the dynamic response of the panels showed the panel time constant to range between 1 and 5 microsec, and the panel capacitance to be between .01 and .02 microF.

Large shaft development test plan

International Nuclear Information System (INIS)

Krug, A.D.

1984-03-01

This test plan proposes the conduct of a large shaft development test at the Hanford site in support of the repository development program. The purpose and objective of the test plan is to obtain the information necessary to establish feasibility and to predict the performance of the drilling system used to drill large diameter shafts. The test plan is based upon drilling a 20 ft diameter shaft to a depth of 1,000 feet. The test plan specifies series of tests to evaluate the performance of the downhole assembly, the performance of the rig, and the ability of the system to cope with geologic hazards. The quality of the hole produced will also be determined. This test plan is considered to be preliminary in that it was prepared as input for the decision to determine if development testing is required in this area. Should the decision be made to proceed with development testing, this test plan shall be updated and revised. 6 refs., 2 figs., 3 tabs

Gallium-cladding compatibility testing plan. Phases 1 and 2: Test plan for gallium corrosion tests. Revision 2

International Nuclear Information System (INIS)

Wilson, D.F.; Morris, R.N.

1998-05-01

This test plan is a Level-2 document as defined in the Fissile Materials Disposition Program Light-Water-Reactor Mixed-Oxide Fuel Irradiation Test Project Plan. The plan summarizes and updates the projected Phases 1 and 2 Gallium-Cladding compatibility corrosion testing and the following post-test examination. This work will characterize the reactions and changes, if any, in mechanical properties that occur between Zircaloy clad and gallium or gallium oxide in the temperature range 30--700 C

Mercury flow tests (first report). Wall friction factor measurement tests and future tests plan

International Nuclear Information System (INIS)

Kaminaga, Masanori; Kinoshita, Hidetaka; Haga, Katsuhiro; Hino, Ryutaro; Sudo, Yukio

1999-07-01

In the neutron science project at JAERI, we plan to inject a pulsed proton beam of a maximum power of 5 MW from a high intense proton accelerator into a mercury target in order to produce high energy neutrons of a magnitude of ten times or more than existing facilities. The neutrons produced by the facility will be utilized for advanced field of science such as the life sciences etc. An urgent issue in order to accomplish this project is the establishment of mercury target technology. With this in mind, a mercury experimental loop with the capacity to circulate mercury up to 15 L/min was constructed to perform thermal hydraulic tests, component tests and erosion characteristic tests. A measurement of the wall friction factor was carried out as a first step of the mercury flow tests, while testing the characteristic of components installed in the mercury loop. This report presents an outline of the mercury loop and experimental results of the wall friction factor measurement. From the wall friction factor measurement, it was made clear that the wettability of the mercury was improved with an increase of the loop operation time and at the same time the wall friction factors were increased. The measured wall friction factors were much lower than the values calculated by the Blasius equation at the beginning of the loop operation because of wall slip caused by a non-wetted condition. They agreed well with the values calculated by the Blasius equation within a deviation of 10% when the sum of the operation time increased more than 11 hours. This report also introduces technical problems with a mercury circulation and future tests plan indispensable for the development of the mercury target. (author)

Tunnel boring waste test plan

International Nuclear Information System (INIS)

Patricio, J.G.

1984-03-01

The test plan has been prepared in anticipation of the need to excavate certain repository openings by relying upon mechanical excavation techniques. The test plan proposes that specific technical issues can be resolved and key design parameters defined by excavating openings in basalt near the surface, utilizing a full face tunnel boring machine (TBM). The purpose and objective of this type of testing will define the overall feasibility and attributes of mechanical excavation in basalt. The test plan recognizes that although this technology is generally available for underground construction for some geologic settings, the current state of technology for excavation in basalt is limited and the potential for improvement is considerable. The test plan recommends that it is economically advantageous to conduct additional testing in the laboratory to allow refinement of this plan based on the laboratory results. Thus, this test plan is considered preliminary in nature, with respect to detailed testing recommendations. However, the gross design attributes and resource requirements of a near-surface TBM demonstration are considered to be valid. 15 refs., 7 figs., 3 tabs

30 CFR 282.23 - Testing Plan.

Science.gov (United States)

2010-07-01

... 30 Mineral Resources 2 2010-07-01 2010-07-01 false Testing Plan. 282.23 Section 282.23 Mineral... § 282.23 Testing Plan. All testing activities shall be conducted in accordance with a Testing Plan... detailed Mining Plan than is obtainable under an approved Delineation Plan, to prepare feasibility studies...

Computer-aided dispatch--traffic management center field operational test final evaluation plan : WSDOT deployment

Science.gov (United States)

2003-09-22

This document presents the Evaluation Teams plan for conducting the evaluation of the FOT in Washington State. A companion document exists for the evaluation of the Utah deployment. This plan includes the experimental design for testing hypotheses...

In-situ tuff water migration/heater experiment: experimental plan

International Nuclear Information System (INIS)

Johnstone, J.K.

1980-08-01

Tuffs on the Nevada Test Site (NTS) are currently under investigation as a potential isolation medium for heat-producing nuclear wastes. The National Academy of Sciences has concurred in our identification of the potentially large water content (less than or equal to 40 vol %) of tuffs as one of the important issues affecting their suitability for a repository. This Experimental Plan describes an in-situ experiment intended as an initial assessment of water generation/migration in response to a thermal input. The experiment will be conducted in the Grouse Canyon Welded Tuff in Tunnel U12g (G-Tunnel) located in the north-central region of the NTS. While the Grouse Canyon Welded Tuff is not a potential repository medium, it has physical, thermal, and mechanical properties very similar to those tuffs currently under consideration and is accessible at depth (400 m below the surface) in an existing facility. Other goals of the experiment are to support computer-code and instrumentation development, and to measure in-situ thermal properties. The experimental array consists of a central electrical heater, 1.2 m long x 10.2 cm diameter, surrounded by three holes for measuring water-migration behavior, two holes for measuring temperature profiles, one hole for measuring thermally induced stress in the rock, and one hole perpendicular to the heater to measure displacement with a laser. This Experimental Plan describes the experimental objectives, the technical issues, the site, the experimental array, thermal and thermomechanical modeling results, the instrumentation, the data-acquisition system, posttest characterization, and the organizational details

Large shaft development test plan

International Nuclear Information System (INIS)

Krug, A.D.

1984-03-01

This test plan proposes the conduct of shaft liner tests as part of the large shaft development test proposed for the Hanford Site in support of the repository development program. The objectives of these tests are to develop techniques for measuring liner alignment (straightness), both construction assembly alignment and downhole cumulative alignment, and to assess the alignment information as a real time feedback to aid the installation procedure. The test plan is based upon installing a 16 foot ID shaft liner into a 20 foot diameter shaft to a depth of 1000 feet. This test plan is considered to be preliminary in that it was prepared as input for the decision to determine if development testing is required in this area. Should the decision be made to proceed with development testing, this test plan shall be updated and revised. 6 refs., 2 figs

Test plans for availability

International Nuclear Information System (INIS)

Rise, J.L.; Bjoerklund, O.

1978-12-01

In this work is developed principles for statistical test plans for availability compliance tests. Failure terminated and time terminated fixed size plans are considered as well as sequential test plans without and with failure and time truncation. The suggested methods are evaluated with respect to some important characteristics, namely the average number of failures to termination, the duration of the test and the operating characteristic function. The methods used are based on the assumption that up- and down-times can be considered gamma distributed. Simulation studies indicate that the methods are robust against reasonable deviations in distribution assumptions for the down-times. In the work is also outlined technical conditions and prerequisites applicable to availability compliance tests in general. The approach choosen seems very promising and is worth further development. It is based on the same fundamental principles as present is used in International standardization of equipment reliability testing. (author)

Digface characterization test plan (remote testing)

International Nuclear Information System (INIS)

Croft, K.; Hyde, R.; Allen, S.

1993-08-01

The objective of the Digface Characterization (DFC) Remote Testing project is to remotely deploy a sensor head (Mini-Lab) across a digface to determine if it can characterize the contents below the surface. The purpose of this project is to provide a robotics technology that allows removal of workers from hazards, increases speed of operations, and reduces life cycle costs compared to alternate methods and technologies. The Buried Waste Integrated Demonstration (BWID) is funding the demonstration, testing, and evaluation of DFC. This document describes the test plan for the DFC remote deployment demonstration for the BWID. The purposes of the test plan are to establish test parameters so that the demonstration results are deemed useful and usable and perform the demonstration in a safe manner and within all regulatory requirements

LASL experimental engineered waste burial facility: design considerations and preliminary plan

International Nuclear Information System (INIS)

DePoorter, G.L.

1980-01-01

The LASL Experimental Engineered Waste Burial Facility is a part of the National Low-Level Waste Management Program on Shallow-Land Burial Technology. It is a test facility where basic information can be obtained on the processes that occur in shallow-land burial operations and where new concepts for shallow-land burial can be tested on an accelerated basis on an appropriate scale. The purpose of this paper is to present some of the factors considered in the design of the facility and to present a preliminary description of the experiments that are initially planned. This will be done by discussing waste management philosophies, the purposes of the facility in the context of the waste management philosophy for the facility, and the design considerations, and by describing the experiments initially planned for inclusion in the facility, and the facility site

VICTORIA Class Submarine Human-in-the-Loop Experimentation Plan

Science.gov (United States)

2014-06-01

1472G. VICTORIA Class Submarine Human-in-the-Loop Experimentation Plan and Preliminary Results © Her Majesty the Queen in Right of...19 th International Command and Control Research and Technology Symposium Title: VICTORIA Class Submarine Human-in-the-Loop...TYPE 3. DATES COVERED 00-00-2014 to 00-00-2014 4. TITLE AND SUBTITLE VICTORIA Class Submarine Human-in-the-Loop Experimentation Plan 5a. CONTRACT

Specialist committee's review reports for experimental fast reactor JOYO' MK-III performance tests

International Nuclear Information System (INIS)

Yamashita, Kiyonobu; Okubo, Toshiyuki; Kamide, Hideki

2004-02-01

Performance tests (startup-physics tests and power elevation tests) were planed for experimental fast reactor 'JOYO' MK-III where irradiation performances were upgraded by power increase from 100 to 140 MW. The reactor safety committee of O-arai Engineering Center has established a specialist committee for 'JOYO' MK-III Performance Tests at the first meeting of 2003 on 23th. April 2003, to accomplish the tests successfully. Subjects of the specialist committee were reviews of following items covering a wide range. 1) Contents of modification works. 2) Reflections of functional test results to the plant and facilities. 3) Reflections of safety rule modification to instruction and manual for operation. 4) Quality assurances and pre-calculation for performance test. 5) Inspection plan and its results. 6) Adequacy of performance test plan. 7) Confirmation of performance test results. Before test-starts, the specialist committee has confirmed by reviewing the items from 1) to 6) based on explanations and documents of the Division of Experimental Reactor, that the test plan and pre-inspections are adequate. After the tests, the specialist committee had confirmed by reviewing the item 7) in the same way, that the each test result satisfies the corresponding criterion. The specialist committee has concluded from these review's results before and after the tests that the 'JOYO' MK-III Performance Tests were carried out appropriately. Besides, the first criticality of the JOYO MK-III was achieved on 2nd. July 2003, and the continuous full power operation was carried on 20th. Nov. 2003. Finally, all performance tests were completed by the pass of the last governmental pre-serviced inspection (dose rate measurement during the shut down condition). (author)

Water NSTF Design, Instrumentation, and Test Planning

Energy Technology Data Exchange (ETDEWEB)

Lisowski, Darius D.; Gerardi, Craig D.; Hu, Rui; Kilsdonk, Dennis J.; Bremer, Nathan C.; Lomperski, Stephen W.; Kraus, Adam R.; Bucknor, Matthew D.; Lv, Qiuping; Farmer, Mitchell T.

2017-08-01

The following report serves as a formal introduction to the water-based Natural convection Shutdown heat removal Test Facility (NSTF) program at Argonne. Since 2005, this US Department of Energy (DOE) sponsored program has conducted large scale experimental testing to generate high-quality and traceable validation data for guiding design decisions of the Reactor Cavity Cooling System (RCCS) concept for advanced reactor designs. The most recent facility iteration, and focus of this report, is the operation of a 1/2 scale model of a water-RCCS concept. Several features of the NSTF prototype align with the conceptual design that has been publicly released for the AREVA 625 MWt SC-HTGR. The design of the NSTF also retains all aspects common to a fundamental boiling water thermosiphon, and thus is well poised to provide necessary experimental data to advance basic understanding of natural circulation phenomena and contribute to computer code validation. Overall, the NSTF program operates to support the DOE vision of aiding US vendors in design choices of future reactor concepts, advancing the maturity of codes for licensing, and ultimately developing safe and reliable reactor technologies. In this report, the top-level program objectives, testing requirements, and unique considerations for the water cooled test assembly are discussed, and presented in sufficient depth to support defining the program’s overall scope and purpose. A discussion of the proposed 6-year testing program is then introduced, which outlines the specific strategy and testing plan for facility operations. The proposed testing plan has been developed to meet the toplevel objective of conducting high-quality test operations that span across a broad range of single- and two-phase operating conditions. Details of characterization, baseline test cases, accident scenario, and parametric variations are provided, including discussions of later-stage test cases that examine the influence of geometric

Nuclear Test-Experimental Science

International Nuclear Information System (INIS)

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B.

1988-01-01

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program

Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Potable Water System Operations Plan

Energy Technology Data Exchange (ETDEWEB)

Ocampo, Ruben P. [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States); Bellah, Wendy [Lawrence Livermore National Lab. (LLNL), Livermore, CA (United States)

2016-03-04

The existing Lawrence Livermore National Laboratory (LLNL) Site 300 drinking water system operation schematic is shown in Figures 1 and 2 below. The sources of water are from two Site 300 wells (Well #18 and Well #20) and San Francisco Public Utilities Commission (SFPUC) Hetch-Hetchy water through the Thomas shaft pumping station. Currently, Well #20 with 300 gallons per minute (gpm) pump capacity is the primary source of well water used during the months of September through July, while Well #18 with 225 gpm pump capacity is the source of well water for the month of August. The well water is chlorinated using sodium hypochlorite to provide required residual chlorine throughout Site 300. Well water chlorination is covered in the Lawrence Livermore National Laboratory Experimental Test Site (Site 300) Chlorination Plan (“the Chlorination Plan”; LLNL-TR-642903; current version dated August 2013). The third source of water is the SFPUC Hetch-Hetchy Water System through the Thomas shaft facility with a 150 gpm pump capacity. At the Thomas shaft station the pumped water is treated through SFPUC-owned and operated ultraviolet (UV) reactor disinfection units on its way to Site 300. The Thomas Shaft Hetch- Hetchy water line is connected to the Site 300 water system through the line common to Well pumps #18 and #20 at valve box #1.

Test plan for demonstration of Rapid Transuranic Monitoring Laboratory

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1993-06-01

This plan describes tests to demonstrate the capability of the Rapid Transuranic Monitoring Laboratory (RTML) to monitor airborne alpha-emitting radionuclides and analyze soil, smear, and filter samples for alpha- and gamma-emitting radionuclides under field conditions. The RTML will be tested during June 1993 at a site adjacent to the Cold Test Pit at the Radioactive Waste Management Complex at the Idaho National Engineering Laboratory. Measurement systems installed in the RTML that will be demonstrated include two large-area ionization chamber alpha spectrometers, an x-ray/gamma-ray spectrometer, and four alpha continuous air monitors. Test objectives, requirements for data quality, experimental apparatus and procedures, and safety and logistics issues are described

STUDENT PLANNING TIME IN ORAL TESTS

Institute of Scientific and Technical Information of China (English)

WangLei

2004-01-01

This paper describes the process of planning in an oral test situation. Since many researchers have studied the impact of pretask planning in the Second Language Acquisition (SLA) field and some have explored the same subject into the area of oral tests, the present study tries to make a tentative attempt to see what the test takers are actually doing in the planning time while taking an oral test. A questionnaire was designed with the effort to find out whether planning time results in an increased focus on form, particularly at the level of strategic attention to form.The result of the investigation tells us that restricted by the type of situation, test takers can only plan the framework of what they are going to say, which may differ to the results achieved by previous studies.

Test plan for Tank 241-AW-101 solubility screening tests

International Nuclear Information System (INIS)

Person, J.C.

1998-01-01

Tank 241-AW-101 (101-AW) has been identified as one of the early tanks to be for retrieved for low level waste pretreatment and immobilization and retrieval of the tank waste may require dilution. This test is to determine the effects of dilution on the mass of solids and their composition. This test plan gives test instructions, example data sheets, a waste compatibility review, and a waste stream fact sheet. This test Plan is similar to tests on tanks 241-AN-102 (Person 1998a) and 241-AN-107 (Person 1998 b). The 101-AW tests will be done with composites of liquid and solids from grab samples that were taken in 1998 (Benar 1998). Future revisions of the Tank Sampling and Analysis Plan (Benar 1998) may change the details of the work performed under this test plan

Project Management Plan for the Idaho National Engineering Laboratory Waste Isolation Pilot Plant Experimental Test Program

International Nuclear Information System (INIS)

Connolly, M.J.; Sayer, D.L.

1993-11-01

EG ampersand G Idaho, Inc. and Argonne National Laboratory-West (ANL-W) are participating in the Idaho National Engineering Laboratory's (INEL's) Waste Isolation Pilot Plant (WIPP) Experimental Test Program (WETP). The purpose of the INEL WET is to provide chemical, physical, and radiochemical data on transuranic (TRU) waste to be stored at WIPP. The waste characterization data collected will be used to support the WIPP Performance Assessment (PA), development of the disposal No-Migration Variance Petition (NMVP), and to support the WIPP disposal decision. The PA is an analysis required by the Code of Federal Regulations (CFR), Title 40, Part 191 (40 CFR 191), which identifies the processes and events that may affect the disposal system (WIPP) and examines the effects of those processes and events on the performance of WIPP. A NMVP is required for the WIPP by 40 CFR 268 in order to dispose of land disposal restriction (LDR) mixed TRU waste in WIPP. It is anticipated that the detailed Resource Conservation and Recovery Act (RCRA) waste characterization data of all INEL retrievably-stored TRU waste to be stored in WIPP will be required for the NMVP. Waste characterization requirements for PA and RCRA may not necessarily be identical. Waste characterization requirements for the PA will be defined by Sandia National Laboratories. The requirements for RCRA are defined in 40 CFR 268, WIPP RCRA Part B Application Waste Analysis Plan (WAP), and WIPP Waste Characterization Program Plan (WWCP). This Project Management Plan (PMP) addresses only the characterization of the contact handled (CH) TRU waste at the INEL. This document will address all work in which EG ampersand G Idaho is responsible concerning the INEL WETP. Even though EG ampersand G Idaho has no responsibility for the work that ANL-W is performing, EG ampersand G Idaho will keep a current status and provide a project coordination effort with ANL-W to ensure that the INEL, as a whole, is effectively and

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). This experimental-waste characterization program is only one part of the WIPP Test Phase, both in the short- and long-term, to quantify and evaluate the characteristics and behavior of transuranic (TRU) wastes in the repository environment. Other parts include the bin-scale and alcove tests, drum-scale tests, and laboratory experiments. In simplified terms, the purpose of the Program is to provide chemical, physical, and radiochemical data describing the characteristics of the wastes that will be emplaced in the WIPP, while the remaining WIPP Test Phase is directed at examining the behavior of these wastes in the repository environment. 50 refs., 35 figs., 33 tabs

Evapotranspiration studies for protective barriers: Experimental plans

International Nuclear Information System (INIS)

Link, S.O.; Waugh, W.J.

1989-11-01

This document describes a general theory and experimental plans for predicting evapotranspiration in support of the Protective Barrier Program. Evapotranspiration is the combined loss of water from plants and soil surfaces to the atmosphere. 45 refs., 1 fig., 4 tabs

Test plan: Potash Core Test. WIPP experimental program borehole plugging

International Nuclear Information System (INIS)

Christensen, C.L.

1979-09-01

The Potash Core Test will utilize a WIPP emplaced plug to obtain samples of an in-situ cured plug of known mix constituents for bench scale testing. An earlier effort involved recovery at the salt horizon of Plug 217, a 17 year old plug in a potash exploration hole for bond testing, but the lack of particulars in the emplacement precluded significant determination of plug performance

Waste feed delivery test and evaluation plan

Energy Technology Data Exchange (ETDEWEB)

O' TOOLE, S.M.

1999-09-30

This plan documents the Waste Feed Delivery Program test and evaluation planning and implementation approach. The purpose of this document is to define and communicate the Waste Feed Delivery Program Test and Evaluation scope, objectives, planning and implementation approach.

Waste feed delivery test and evaluation plan

International Nuclear Information System (INIS)

O'TOOLE, S.M.

1999-01-01

This plan documents the Waste Feed Delivery Program test and evaluation planning and implementation approach. The purpose of this document is to define and communicate the Waste Feed Delivery Program Test and Evaluation scope, objectives, planning and implementation approach

Fabrication, inspection, and test plan for the Advanced Test Reactor (ATR) Mixed-Oxide (MOX) fuel irradiation project

International Nuclear Information System (INIS)

Wachs, G.W.

1997-11-01

The Department of Energy (DOE) Fissile Materials Disposition Materials Disposition Program (FMDP) has announced that reactor irradiation of MOX fuel is one of the preferred alternatives for disposal of surplus weapons-usable plutonium (Pu). MOX fuel has been utilized domestically in test reactors and on an experimental basis in a number of Commercial Light Water Reactors (CLWRs). Most of this experience has been with Pu derived from spent low enriched uranium (LEU) fuel, known as reactor grade (RG) Pu. The MOX fuel test will be irradiated in the ATR to provide preliminary data to demonstrate that the unique properties of surplus weapons-derived or weapons-grade (WG) plutonium (Pu) do not compromise the applicability of this MOX experience base. In addition, the test will contribute experience with irradiation of gallium-containing fuel to the data base required for resolution of generic CLWR fuel design issues (ORNL/MD/LTR-76). This Fabrication, Inspection, and Test Plan (FITP) is a level 2 document as defined in the FMDP LWR MOX Fuel Irradiation Test Project Plan (ORNL/MD/LTR-78)

Test Plan: Phase 1, Hanford LLW melter tests, GTS Duratek, Inc

International Nuclear Information System (INIS)

Eaton, W.C.

1995-01-01

This document provides a test plan for the conduct of vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384215] is GTS Duratek, Inc., Columbia, Maryland. The GTS Duratek project manager for this work is J. Ruller. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass with Hanford LLW Double-Shell Slurry Feed waste simulant in a DuraMelter trademark vitrification system

Energy Systems Test Area (ESTA) Battery Test Operations User Test Planning Guide

Science.gov (United States)

Salinas, Michael

2012-01-01

Test process, milestones and inputs are unknowns to first-time users of the ESTA Battery Test Operations. The User Test Planning Guide aids in establishing expectations for both NASA and non-NASA facility customers. The potential audience for this guide includes both internal and commercial spaceflight hardware/software developers. It is intended to assist their test engineering personnel in test planning and execution. Material covered includes a roadmap of the test process, roles and responsibilities of facility and user, major milestones, facility capabilities, and inputs required by the facility. Samples of deliverables, test article interfaces, and inputs necessary to define test scope, cost, and schedule are included as an appendix to the guide.

PREPARE: guidelines for planning animal research and testing.

Science.gov (United States)

Smith, Adrian J; Clutton, R Eddie; Lilley, Elliot; Hansen, Kristine E Aa; Brattelid, Trond

2018-04-01

There is widespread concern about the quality, reproducibility and translatability of studies involving research animals. Although there are a number of reporting guidelines available, there is very little overarching guidance on how to plan animal experiments, despite the fact that this is the logical place to start ensuring quality. In this paper we present the PREPARE guidelines: Planning Research and Experimental Procedures on Animals: Recommendations for Excellence. PREPARE covers the three broad areas which determine the quality of the preparation for animal studies: formulation, dialogue between scientists and the animal facility, and quality control of the various components in the study. Some topics overlap and the PREPARE checklist should be adapted to suit specific needs, for example in field research. Advice on use of the checklist is available on the Norecopa website, with links to guidelines for animal research and testing, at https://norecopa.no/PREPARE .

MATLAB platform for Monte Carlo planning and dosimetry experimental evaluation

International Nuclear Information System (INIS)

Baeza, J. A.; Ureba, A.; Jimenez-Ortega, E.; Pereira-Barbeiro, A. R.; Leal, A.

2013-01-01

A new platform for the full Monte Carlo planning and an independent experimental evaluation that it can be integrated into clinical practice. The tool has proved its usefulness and efficiency and now forms part of the flow of work of our research group, the tool used for the generation of results, which are to be suitably revised and are being published. This software is an effort of integration of numerous algorithms of image processing, along with planning optimization algorithms, allowing the process of MCTP planning from a single interface. In addition, becomes a flexible and accurate tool for the evaluation of experimental dosimetric data for the quality control of actual treatments. (Author)

Test Plan: Sludge Treatment Project Corrosion Process Chemistry Follow-on Testing

Energy Technology Data Exchange (ETDEWEB)

Delegard, Calvin H.; Schmidt, Andrew J.; Poloski, Adam P.

2007-08-17

This test plan was prepared by the Pacific Northwest National Laboratory (PNNL) under contract with Fluor Hanford (FH). The test plan describes the scope and conditions to be used to perform laboratory-scale testing of the Sludge Treatment Project (STP) hydrothermal treatment of K Basin sludge. The STP, managed for the U. S. Department of Energy (DOE) by FH, was created to design and operate a process to eliminate uranium metal from the sludge prior to packaging for Waste Isolation Pilot Plant (WIPP) by using high temperature liquid water to accelerate the reaction, produce uranium dioxide from the uranium metal, and safely discharge the hydrogen. The proposed testing builds on the approach and laboratory test findings for both K Basin sludge and simulated sludge garnered during prior testing from September 2006 to March 2007. The outlined testing in this plan is designed to yield further understanding of the nature of the chemical reactions, the effects of compositional and process variations and the effectiveness of various strategies to mitigate the observed high shear strength phenomenon observed during the prior testing. These tests are designed to provide process validation and refinement vs. process development and design input. The expected outcome is to establish a level of understanding of the chemistry such that successful operating strategies and parameters can be implemented within the confines of the existing STP corrosion vessel design. In July 2007, the DOE provided direction to FH regarding significant changes to the scope of the overall STP. As a result of the changes, FH directed PNNL to stop work on most of the planned activities covered in this test plan. Therefore, it is unlikely the testing described here will be performed. However, to preserve the test strategy and details developed to date, the test plan has been published.

AFFTC Instruction 99-1, Test and Evaluation Test Plans

National Research Council Canada - National Science Library

Crane, Roger

2002-01-01

.... Test Information Sheets (TISs) are actually appendices to test plans and contain sufficient information for use by a flight test engineer to develop flight test cards and for management to discern the overall technical approach being taken...

Light Duty Utility Arm system pre-operational (cold test) test plan

International Nuclear Information System (INIS)

Bennett, K.L.

1995-01-01

The Light Duty Utility (LDUA) Cold Test Facility, located in the Hanford 400 Area, will be used to support cold testing (pre- operational tests) of LDUA subsystems. Pre-operational testing is composed of subsystem development testing and rework activities, and integrated system qualification testing. Qualification testing will be conducted once development work is complete and documentation is under configuration control. Operational (hot) testing of the LDUA system will follow the testing covered in this plan and will be covered in a separate test plan

Acceptance Test Plan for ANSYS Software

International Nuclear Information System (INIS)

CREA, B.A.

2000-01-01

This plan governs the acceptance testing of the ANSYS software (Full Mechanical Release 5.5) for use on Project Word Management Contract (PHMC) computer systems (either UNIX or Microsoft Windows/NT). There are two phases to the acceptance testing covered by this test plan: program execution in accordance with the guidance provided in installation manuals; and ensuring results of the execution are consistent with the expected physical behavior of the system being modeled

Addendum to ''Test Plan: Small-Scale Seal Performance Tests (SSSPT)''

International Nuclear Information System (INIS)

Finley, R.E.

1992-01-01

This document describes activities that are intended to update the data base of fluid flow measurements made on expansive salt concrete (ESC) seals as part of the Small-Scale Seal Performance Tests (SSSPT). The original plans for the SSSPT experiments are described by Stormont (1985a and 1985b). These seals have previously been tested with brine and gas during the early stages (less than 450 days) after emplacement. The purpose of this Test Plan Addendum is to detail the activities necessary to, update the gas and brine measurements previously performed on the SSSPT Series A and Series B seals and to identify the key personnel responsible for implementing these activities. This addendum describes a limited undertaking and does NOT change the scope of the original test plan

Experimental and Sampling Design for the INL-2 Sample Collection Operational Test

Energy Technology Data Exchange (ETDEWEB)

Piepel, Gregory F.; Amidan, Brett G.; Matzke, Brett D.

2009-02-16

This report describes the experimental and sampling design developed to assess sampling approaches and methods for detecting contamination in a building and clearing the building for use after decontamination. An Idaho National Laboratory (INL) building will be contaminated with BG (Bacillus globigii, renamed Bacillus atrophaeus), a simulant for Bacillus anthracis (BA). The contamination, sampling, decontamination, and re-sampling will occur per the experimental and sampling design. This INL-2 Sample Collection Operational Test is being planned by the Validated Sampling Plan Working Group (VSPWG). The primary objectives are: 1) Evaluate judgmental and probabilistic sampling for characterization as well as probabilistic and combined (judgment and probabilistic) sampling approaches for clearance, 2) Conduct these evaluations for gradient contamination (from low or moderate down to absent or undetectable) for different initial concentrations of the contaminant, 3) Explore judgment composite sampling approaches to reduce sample numbers, 4) Collect baseline data to serve as an indication of the actual levels of contamination in the tests. A combined judgmental and random (CJR) approach uses Bayesian methodology to combine judgmental and probabilistic samples to make clearance statements of the form "X% confidence that at least Y% of an area does not contain detectable contamination” (X%/Y% clearance statements). The INL-2 experimental design has five test events, which 1) vary the floor of the INL building on which the contaminant will be released, 2) provide for varying the amount of contaminant released to obtain desired concentration gradients, and 3) investigate overt as well as covert release of contaminants. Desirable contaminant gradients would have moderate to low concentrations of contaminant in rooms near the release point, with concentrations down to zero in other rooms. Such gradients would provide a range of contamination levels to challenge the sampling

Test plan for FY-91 dust control studies

International Nuclear Information System (INIS)

Winberg, M.R.

1991-03-01

This test plan defines basic test procedures for testing commercially available vendor products as soil fixatives and dust suppression agents to determine their capability to control fugitive dust generation during transuranic waste retrieval and handling operations. A description of the test apparatus and methods are provided in this test plan. This test plan defines the sampling procedures, controls, and analytical methods for the samples collected. Data management is discussed, as well as quality assurance and safety requirements for the study. 6 refs., 5 figs

Nevada Test Site Experimental Farm: summary report 1963-1981

International Nuclear Information System (INIS)

Black, S.C.; Smith, D.D.

1984-08-01

This report summarizes the findings from experiments conducted at the Experimental Dairy Farm located on the Nevada Test Site. These experiments included the air-forage-cow-milk transport of the radioiodines, and the metabolism and milk transfer of other fission products and several actinides. Major studies are listed in chronological order from 1964 to 1978 and include the purpose, procedures, isotopes used, and findings for each such study. Animal exposures occurred from fallout, from artificial aerosol generation, and from oral or intravenous administration. A complete bibliography and references to published reports of the experiments are included. The findings from the radioisotope studies at the Experimental Dairy Farm and the results obtained from the Animal Investigation Program provide a rationale for making predictions and for planning protective actions that could be useful in emergency response to accidental contaminating events where fresh fission products are involved. 61 references

Experimental area plans for an advanced hadron facility

Energy Technology Data Exchange (ETDEWEB)

Hoffman, E.W.; Macek, R.J.; Tschalear, C.

1986-01-01

A brief overview is presented of the current plans for an experimental area for a new advanced hadron facility for the exploration of nuclear and particle physics. The facility, LAMPF II, is presently visualized as consisting of the LAMPF linac sending 800 MeV protons to a 6 GeV booster ring followed by a 45 GeV main ring. Two experimental areas area planned. The first is intended to provide neutrinos via a pair of pulsed focusing horns. The other is designed to accommodate secondary beams that span the range of useful energies up to GeV/c. Beam specification goals are discussed with respect to source brightness, beam purity, and beam-line acceptance and length. The various beam lines are briefly described. Production cross sections and rates are estimated for antiproton production. Problems of thermal energy deposition in both components and targets and of effectiveness of particle separators are discussed. 9 refs. (LEW)

Experimental area plans for an advanced hadron facility

International Nuclear Information System (INIS)

Hoffman, E.W.; Macek, R.J.; Tschalear, C.

1986-01-01

A brief overview is presented of the current plans for an experimental area for a new advanced hadron facility for the exploration of nuclear and particle physics. The facility, LAMPF II, is presently visualized as consisting of the LAMPF linac sending 800 MeV protons to a 6 GeV booster ring followed by a 45 GeV main ring. Two experimental areas area planned. The first is intended to provide neutrinos via a pair of pulsed focusing horns. The other is designed to accommodate secondary beams that span the range of useful energies up to GeV/c. Beam specification goals are discussed with respect to source brightness, beam purity, and beam-line acceptance and length. The various beam lines are briefly described. Production cross sections and rates are estimated for antiproton production. Problems of thermal energy deposition in both components and targets and of effectiveness of particle separators are discussed. 9 refs

Using Optimization to Improve Test Planning

Science.gov (United States)

2017-09-01

OPTIMIZATION TO IMPROVE TEST PLANNING by Arlene M. Payne September 2017 Thesis Advisor: Jeffrey E. Kline Second Reader: Oleg A. Yakimenko THIS... Project (0704-0188) Washington, DC 20503. 1. AGENCY USE ONLY (Leave blank) 2. REPORT DATE September 2017 3. REPORT TYPE AND DATES COVERED Master’s...thesis 4. TITLE AND SUBTITLE USING OPTIMIZATION TO IMPROVE TEST PLANNING 5. FUNDING NUMBERS 6. AUTHOR(S) Arlene M. Payne 7. PERFORMING ORGANIZATION

Critical considerations when planning experimental in vivo studies in dental traumatology.

Science.gov (United States)

Andreasen, Jens O; Andersson, Lars

2011-08-01

In vivo studies are sometimes needed to understand healing processes after trauma. For several reasons, not the least ethical, such studies have to be carefully planned and important considerations have to be taken into account about suitability of the experimental model, sample size and optimizing the accuracy of the analysis. Several manuscripts of in vivo studies are submitted for publication to Dental Traumatology and rejected because of inadequate design, methodology or insufficient documentation of the results. The authors have substantial experience in experimental in vivo studies of tissue healing in dental traumatology and share their knowledge regarding critical considerations when planning experimental in vivo studies. © 2011 John Wiley & Sons A/S.

Quality Assurance Program Plan for the Waste Isolation Pilot Plant Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-01-01

This Quality Assurance Program Plan (QAPP) identifies the quality of data necessary to meet the specific objectives associated with the Department of Energy (DOE) Waste Isolation Pilot Plant (WIPP) Experimental-Waste Characterization Program (the Program). DOE plans to conduct experiments in the WIPP during a Test Phase of approximately 5 years. These experiments will be conducted to reduce the uncertainties associated with the prediction of several processes (e.g., gas generation) that may influence repository performance. The results of the experiments will be used to assess the ability of the WIPP to meet regulatory requirements for the long-term protection of human health and the environment from the disposal of TRU wastes. 37 refs., 25 figs., 18 tabs

Energy Systems Test Area (ESTA) Electrical Power Systems Test Operations: User Test Planning Guide

Science.gov (United States)

Salinas, Michael J.

2012-01-01

Test process, milestones and inputs are unknowns to first-time users of the ESTA Electrical Power Systems Test Laboratory. The User Test Planning Guide aids in establishing expectations for both NASA and non-NASA facility customers. The potential audience for this guide includes both internal and commercial spaceflight hardware/software developers. It is intended to assist their test engineering personnel in test planning and execution. Material covered includes a roadmap of the test process, roles and responsibilities of facility and user, major milestones, facility capabilities, and inputs required by the facility. Samples of deliverables, test article interfaces, and inputs necessary to define test scope, cost, and schedule are included as an appendix to the guide.

Integration and test planning patterns in different organizations

NARCIS (Netherlands)

Jong, de I.S.M.; Boumen, R.; Mortel - Fronczak, van de J.M.; Rooda, J.E.; Tretmans, J.

2007-01-01

Planning an integration and test phase is often done by experts in the visited organizations. These experts have a thorough knowledge about the system, integration and testing and the business drivers of an organization. An integration and test plan developedfor an airplane is different than the

Test Plan: WIPP bin-scale CH TRU waste tests

International Nuclear Information System (INIS)

Molecke, M.A.

1990-08-01

This WIPP Bin-Scale CH TRU Waste Test program described herein will provide relevant composition and kinetic rate data on gas generation and consumption resulting from TRU waste degradation, as impacted by synergistic interactions due to multiple degradation modes, waste form preparation, long-term repository environmental effects, engineered barrier materials, and, possibly, engineered modifications to be developed. Similar data on waste-brine leachate compositions and potentially hazardous volatile organic compounds released by the wastes will also be provided. The quantitative data output from these tests and associated technical expertise are required by the WIPP Performance Assessment (PA) program studies, and for the scientific benefit of the overall WIPP project. This Test Plan describes the necessary scientific and technical aspects, justifications, and rational for successfully initiating and conducting the WIPP Bin-Scale CH TRU Waste Test program. This Test Plan is the controlling scientific design definition and overall requirements document for this WIPP in situ test, as defined by Sandia National Laboratories (SNL), scientific advisor to the US Department of Energy, WIPP Project Office (DOE/WPO). 55 refs., 16 figs., 19 tabs

Surface moisture measurement system acceptance testing work plan

International Nuclear Information System (INIS)

Ritter, G.A.

1996-01-01

This work plan addresses testing of the Surface Moisture Measurement System (SMMS) at the Fuels and Materials Examination Facility (FMEF). The purpose of this plan is to define the scope of work, identify organizational responsibilities, describe test control requirements, and provide estimated costs and schedule associated with acceptance testing

Developing test for experimental study: the effectiveness of hedwig strategy in english education department universitas brawijaya

Directory of Open Access Journals (Sweden)

Devinta Puspita Ratri

2017-04-01

Having a big number of students in content subject of a language class is a challenge for teacher since it is quite difficult to accommodate students’ critical thinking and active participation at the same time. Therefore, Hedwig strategy is aimed to give room for students to explore themselves and get involved in the materials delivered in the class. Furthermore, by having group and regroup to deliver message in Hedwig strategy, students are forced to be active participated in classroom activities. The idea of Hedwig strategy is inspired by Jigsaw and Think-Pair-Share which have existed before. To know whether Hedwig strategy is effectively applied in content subject in large language class, it is proposed to do quasi experimental study with one class as an experimental group and one class as a control group. The experimental group is treated by using Hedwig strategy. Prior to the experimental study, it is performed research and development to develop the test for pre-test and post-test. For that reason, the research problem is what test is valid and reliable for an experimental study on the effectiveness of Hedwig strategy for the 4th semester students in Language Teaching Methodology class in English Education Department Universitas Brawijaya. This research reports half of the whole plan where the researchers developed test for pre-test and posttest to measure students’ improvement in understanding Language Teaching Methodology. In short, the test developed in this study will be used to carry out experimental study as pre-test and post-test

Crawler Acquisition and Testing Demonstration Project Management Plan

International Nuclear Information System (INIS)

DEFIGH-PRICE, C.

2000-01-01

If the crawler based retrieval system is selected, this project management plan identifies the path forward for acquiring a crawler/track pump waste retrieval system, and completing sufficient testing to support deploying the crawler for as part of a retrieval technology demonstration for Tank 241-C-104. In the balance of the document, these activities will be referred to as the Crawler Acquisition and Testing Demonstration. During recent Tri-Party Agreement negotiations, TPA milestones were proposed for a sludge/hard heel waste retrieval demonstration in tank C-104. Specifically one of the proposed milestones requires completion of a cold demonstration of sufficient scale to support final design and testing of the equipment (M-45-03G) by 6/30/2004. A crawler-based retrieval system was one of the two options evaluated during the pre-conceptual engineering for C-104 retrieval (RPP-6843 Rev. 0). The alternative technology procurement initiated by the Hanford Tanks Initiative (HTI) project, combined with the pre-conceptual engineering for C-104 retrieval provide an opportunity to achieve compliance with the proposed TPA milestone M-45-03H. This Crawler Acquisition and Testing Demonstration project management plan identifies the plans, organizational interfaces and responsibilities, management control systems, reporting systems, timeline and requirements for the acquisition and testing of the crawler based retrieval system. This project management plan is complimentary to and supportive of the Project Management Plan for Retrieval of C-104 (RPP-6557). This project management plan focuses on utilizing and completing the efforts initiated under the Hanford Tanks Initiative (HTI) to acquire and cold test a commercial crawler based retrieval system. The crawler-based retrieval system will be purchased on a schedule to support design of the waste retrieval from tank C-104 (project W-523) and to meet the requirement of proposed TPA milestone M-45-03H. This Crawler

Experimental test of magnetic photons

International Nuclear Information System (INIS)

Lakes, R.S.

2004-01-01

A 'magnetic' photon hypothesis associated with magnetic monopoles is tested experimentally. These photons are predicted to easily penetrate metal. Experimentally the optical transmittance T of a metal foil was less than 2x10-17. The hypothesis is not supported since it predicts T=2x10-12

ORCWM test and evaluaton master plan. Revision 00

International Nuclear Information System (INIS)

1995-08-01

The Office of Civilian Radioactive Waste Management (OCRWM) Test and Evaluation Master Plan (TEMP) describes the program Test and Evaluation (T ampersand E) policy, objectives, requirements, general methodology (test flow and description of each T ampersand E phase), responsibilities, and scheduling of test phases for the Civilian Radioactive Waste Management System (CRWMS). This TEMP is a program-level management planning document for al CRWMS T ampersand E activities and will be used in conjunction with Section 11 of the Quality Assurance Requirements and Description (QARD), as appropriate, as a guide for the projects in developing their T ampersand E plans. In the OCRWM document hierarchy, that is described in the OCRWM Systems Engineering Management Plan (SEMP), the TEMP is subordinate to the program SEMP. To ensure CRWMS operates as an integrated system, the plans for verifying the performance and evaluating the operational suitability and effectiveness of the overall system are also described. Test and evaluation is an integral part of the systems engineering process. Key aspects of the systems engineering process, more fully described in the OCRWM SEMP, are discussed in this TEMP to illustrate how T ampersand E supports the overall systems engineering process

Testing plan for critical heat flux measurement during in-vessel retention

International Nuclear Information System (INIS)

Aoki, Kazuyoshi; Iwaki, Chikako; Sato, Hisaki; Mimura, Satoshi; Kanamori, Daisuke

2015-01-01

In-Vessel Retention (IVR) is a method to maintain molten debris in a reactor vessel (RV) by RV outer surface cooling. Structural integrity of RV and cooling capacity on RV outer surface are important to verify IVR strategy. Critical Heat Flux (CHF) data is necessary to estimate cooling capacity on the RV outer surface. And there are some CHF data to estimate cooling capacity on the RV outer surface. However, these data were obtained for specific plants. Thus, the objective of this study is developing a CHF correlation for various PWR plants. The objectives of this paper are developing test equipment and testing plan for the CHF correlation. Firstly, plant conditions during severe accidents were organized. Then, ranges of testing parameters were estimated with the plant conditions. And specifications of the test equipment were set to cover the range of parameters. Secondly, testing cases were set based on design of experiments. The test cases are suitable to develop experimental correlations. (author)

Six-Degree-of-Freedom Dynamic Test System (SDTS) User Test Planning Guide

Science.gov (United States)

Stokes, LeBarian

2012-01-01

Test process, milestones and inputs are unknowns to first-time users of the SDTS. The User Test Planning Guide aids in establishing expectations for both NASA and non- NASA facility customers. The potential audience for this guide includes both internal and commercial spaceflight hardware/software developers. It is intended to assist their test engineering personnel in test planning and execution. Material covered includes a roadmap of the test process, roles and responsibilities of facility and user, major milestones, facility capabilities, and inputs required by the facility. Samples of deliverables, test article interfaces, and inputs necessary to define test scope, cost, and schedule are included as an appendix to the guide.

Modeling and Field Test Planning Activities in Support of Disposal of Heat-Generating Waste in Salt

Energy Technology Data Exchange (ETDEWEB)

Rutqvist, Jonny; Blanco Martin, Laura; Mukhopadhyay, Sumit; Houseworth, Jim; Birkholzer, Jens

2014-09-26

The modeling efforts in support of the field test planning conducted at LBNL leverage on recent developments of tools for modeling coupled thermal-hydrological-mechanical-chemical (THMC) processes in salt and their effect on brine migration at high temperatures. This work includes development related to, and implementation of, essential capabilities, as well as testing the model against relevant information and published experimental data related to the fate and transport of water. These are modeling capabilities that will be suitable for assisting in the design of field experiment, especially related to multiphase flow processes coupled with mechanical deformations, at high temperature. In this report, we first examine previous generic repository modeling results, focusing on the first 20 years to investigate the expected evolution of the different processes that could be monitored in a full-scale heater experiment, and then present new results from ongoing modeling of the Thermal Simulation for Drift Emplacement (TSDE) experiment, a heater experiment on the in-drift emplacement concept at the Asse Mine, Germany, and provide an update on the ongoing model developments for modeling brine migration. LBNL also supported field test planning activities via contributions to and technical review of framework documents and test plans, as well as participation in workshops associated with field test planning.

Test Room Stability Plan

International Nuclear Information System (INIS)

1993-01-01

This plan documents the combination of designs, installations, programs, and activities that ensures that the underground excavations at the Waste Isolation Pilot Plant (WIPP), in which transuranic (TRU) waste may be emplaced during the Test Phase, will remain sufficiently stable and safe during that time. The current ground support systems installed at the WIPP are the result of over ten years of data collection from hundreds of geomechanical instruments and thousands of hours of direct observation of the changing conditions of the openings. In addition, some of the world's most respected experts on salt rock mechanics have provided input in the design process and concurrence on the suitability of the final design. The general mine rockbolt pattern and the ground support system for the test rooms are designed to specifically address the fracture and deformation geometries observed today at the WIPP. After an introductory chapter, this plan describes the general underground design, then proceeds to an account of general ground support performance, and finally focuses on the details of the special test room ground support systems. One such system already installed in Room 1, Panel 1, is described in comprehensive detail. Other test rooms in Panel 1, whether full-size or smaller, will be equipped with systems that ensure stability to the same or equivalent extent. They will benefit from the experience gained in the first test room, which in turn benefitted from the data and knowledge accumulated during previous stages (e.g., the Site and Preliminary Design Validation program) of the project

Disposal phase experimental program plan

International Nuclear Information System (INIS)

1997-01-01

The Waste Isolation Pilot Plant (WIPP) facility comprises surface and subsurface facilities, including a repository mined in a bedded salt formation at a depth of 2,150 feet. It has been developed to safely and permanently isolate transuranic (TRU) radioactive wastes in a deep geological disposal site. On April 12, 1996, the DOE submitted a revised Resource Conservation and Recovery Act (RCRA) Part B permit application to the New Mexico Environment Department (NMED). The DOE anticipates receiving an operating permit from the NMED; this permit is required prior to the start of disposal operations. On October 29, 1996, the DOE submitted a Compliance Certification Application (CCA) to the US Environmental Protection Agency (EPA) in accordance with the WIPP land Withdrawal Act (LWA) of 1992 (Public Law 102-579) as amended, and the requirements of Title 40 of the Code of Federal Regulations (40 CFR) Parts 191 and 194. The DOE plans to begin disposal operations at the WIPP in November 1997 following receipt of certification by the EPA. The disposal phase is expected to last for 35 years, and will include recertification activities no less than once every five years. This Disposal Phase Experimental Program (DPEP) Plan outlines the experimental program to be conducted during the first 5-year recertification period. It also forms the basis for longer-term activities to be carried out throughout the 35-year disposal phase. Once the WIPP has been shown to be in compliance with regulatory requirements, the disposal phase gives an opportunity to affirm the compliance status of the WIPP, enhance the operations of the WIPP and the national TRU system, and contribute to the resolution of national and international nuclear waste management technical needs. The WIPP is the first facility of its kind in the world. As such, it provides a unique opportunity to advance the technical state of the art for permanent disposal of long-lived radioactive wastes

Surface stability test plan for protective barriers

International Nuclear Information System (INIS)

Ligotke, M.W.

1989-01-01

Natural-material protective barriers for long-term isolation of buried waste have been identified as integral components of a plan to isolate a number of Hanford defense waste sites. Standards currently being developed for internal and external barrier performance will mandate a barrier surface layer that is resistant to the eolian erosion processes of wind erosion (deflation) and windborne particle deposition (formation of sand dunes). Thus, experiments are needed to measure rates of eolian erosion processes impacting those surfaces under different surface and climatological conditions. Data from these studies will provide information for use in the evaluation of selected surface layers as a means of providing stable cover over waste sites throughout the design life span of protective barriers. The multi-year test plan described in this plan is directed at understanding processes of wind erosion and windborne particle deposition, providing measurements of erosion rates for models, and suggesting construction materials and methods for reducing the effect of long-term eolian erosion on the barrier. Specifically, this plan describes possible methods to measure rates of eolian erosion, including field and laboratory procedure. Advantages and disadvantages of laboratory (wind tunnel) tests are discussed, and continued wind tunnel tests are recommended for wind erosion studies. A comparison between field and wind tunnel erosive forces is discussed. Plans for testing surfaces are described. Guidance is also presented for studying the processes controlling sand dune and blowout formation. 24 refs., 7 figs., 3 tabs

Plan of ITER remote experimentation center

Energy Technology Data Exchange (ETDEWEB)

Ozeki, T., E-mail: ozeki.takahisa@jaea.go.jp [Japan Atomic Energy Agency, 2-166 Obuchi Rokkasho, Kitakami-gun, Aomori 039-3212 (Japan); Clement, S.L. [Fusion for Energy, Torres Diagonal Litoral, B3, 13/03, 08019 Barcelona (Spain); Nakajima, N. [National Institute for Fusion Science and Project Leader of IFERC, 2-166 Obuchi, Rokkasho, Kamikita-gun, Aomori 039-3212 (Japan)

2014-05-15

Plan of ITER remote experimentation center (REC) based on the broader approach (BA) activity of the joint program of Japan and Europe (EU) is described. Objectives of REC activity are (1) to identify the functions and solve the technical issues for the construction of the REC for ITER at Rokkasho, (2) to develop the remote experiment system and verify the functions required for the remote experiment by using the Satellite Tokamak (JT-60SA) facilities in order to make the future experiments of ITER and JT-60SA effectively and efficiently implemented, and (3) to test the functions of REC and demonstrate the total system by using JT-60SA and existing other facilities in EU. Preliminary identified items to be developed are (1) Functions of the remote experiment system, such as setting of experiment parameters, shot scheduling, real time data streaming, communication by video-conference between the remote-site and on-site, (2) Effective data transfer system that is capable of fast transfer of the huge amount of data between on-site and off-site and the network connecting the REC system, (3) Storage system that can store/access the huge amount of data, including database management, (4) Data analysis software for the data viewing of the diagnostic data on the storage system, (5) Numerical simulation for preparation and estimation of the shot performance and the analysis of the plasma shot. Detailed specifications of the above items will be discussed and the system will be made in these four years in collaboration with tokamak facilities of JT-60SA and EU tokamak, experts of informatics, activities of plasma simulation and ITER. Finally, the function of REC will be tested and the total system will be demonstrated by the middle of 2017.

Generating custom test plans for CASE{sup *}Dictionary 5.0

Energy Technology Data Exchange (ETDEWEB)

Atkins, K.D. [Boeing Computer Services, Richland, WA (United States)

1994-04-01

Most database development organizations use a formal software development methodology that requires a certain amount of formal testing. The amount of formal testing that will be performed will vary from methodology to methodology and from site to site. If a very detailed formal test plan is required for each module in a system, the work involved to produce the test plan can be tedious and costly. After a system has been designed and developed using Oracle*CASE, there is much useful information in the CASE*Dictionary repository. If this information could be tied to specific test requirements, a test plan could be generated automatically, saving much time and resources. This paper shows how CASE*Dictionary can be used to store test plan information that can then be used to generate a specific test plan for each module based on it`s detailed data usage.

MATLAB platform for Monte Carlo planning and dosimetry experimental evaluation; Plataforma Matlab para planificacion Monte Carlo y evaluacion dosimetrica experimental

Energy Technology Data Exchange (ETDEWEB)

Baeza, J. A.; Ureba, A.; Jimenez-Ortega, E.; Pereira-Barbeiro, A. R.; Leal, A.

2013-07-01

A new platform for the full Monte Carlo planning and an independent experimental evaluation that it can be integrated into clinical practice. The tool has proved its usefulness and efficiency and now forms part of the flow of work of our research group, the tool used for the generation of results, which are to be suitably revised and are being published. This software is an effort of integration of numerous algorithms of image processing, along with planning optimization algorithms, allowing the process of MCTP planning from a single interface. In addition, becomes a flexible and accurate tool for the evaluation of experimental dosimetric data for the quality control of actual treatments. (Author)

Planned Experiments on the Princeton Advanced Test Stand

Science.gov (United States)

Stepanov, A.; Gilson, E. P.; Grisham, L.; Kaganovich, I.; Davidson, R. C.

2010-11-01

The Princeton Advanced Test Stand (PATS) device is an experimental facility based on the STS-100 high voltage test stand transferred from LBNL. It consists of a multicusp RF ion source, a pulsed extraction system capable of forming high-perveance 100keV ion beams, and a large six-foot-long vacuum with convenient access for beam diagnostics. This results in a flexible system for studying high perveance ion beams relevant to NDCX-I/II, including experiments on beam neutralization by ferroelectric plasma sources (FEPS) being developed at PPPL. Research on PATS will concern the basic physics of beam-plasma interactions, such as the effects of volume neutralization on beam emittance, as well as optimizing technology of the FEPS. PATS combines the advantage of an ion beam source and a large-volume plasma source in a chamber with ample access for diagnostics, resulting in a robust setup for investigating and improving relevant aspects of neutralized drift. There are also plans for running the ion source with strongly electro-negative gases such as chlorine, making it possible to extract positive or negative ion beams.

Nevada Test Site Resource Management Plan: Annual summary, January 2000

International Nuclear Information System (INIS)

2000-01-01

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan

Nevada Test Site Resource Management Plan: Annual summary, January 2000

Energy Technology Data Exchange (ETDEWEB)

NONE

2000-01-01

The Nevada Test Site Resource Management Plan published in December of 1998 (DOE/NV--518) describes the Nevada Test Site stewardship mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. As part of the Nevada Test Site Resource Management Plan, DOE Nevada Operations Office has committed to perform and publish an annual summary review of DOE Nevada Operations' stewardship of the Nevada Test Site. This annual summary includes a description of progress made toward the goals of the Nevada Test Site Resource Management Plan, pertinent monitoring data, actions that were taken to adapt to changing conditions, and any other changes to the Nevada Test Site Resource Management Plan.

The importance of pre-planning for large hydrostatic test programs

Energy Technology Data Exchange (ETDEWEB)

Bennett, Andrew Keith [WorleyParsons Calgary, Calgary, AB (Canada); Wong, Everett Clementi [Enbridge Pipelines Inc., Edmonton, AB (Canada)

2010-07-01

During the design phase of a pipeline project, large hydrostatic test programs are required to locate and secure water sources. Many companies complete hydrostatic test planning through high level desktop analysis, however this technique can result in important unplanned costs and schedule delays. The aim of this paper is to assess the cost benefits of pre-planning large hydrostatic test programs versus the costs of unplanned delays in the execution of hydrostatic testing. This comparison was based on the successful application of pre-planning of 57 mainline hydrostatic tests in the construction of the Line 4 Extension and Alberta Clipper Expansion oil pipelines by Enbridge Pipelines Inc. Results showed that costs of delays and uncertainty during construction far outweigh the costs of pre-planning. This study highlighted that pre-planning for large hydrostatic test programs should be carried out in the execution of large pipeline projects to ensure success.

Test plan for spent fuel cladding containment credit tests

International Nuclear Information System (INIS)

Wilson, C.N.

1983-11-01

Lawrence Livermore National Laboratory has chosen Westinghouse Hanford Company as a subcontractor to assist them in determining the requirements for successful disposal of spent fuel rods in the proposed Nevada Test Site repository. An initial scoping test, with the objective of determining whether or not the cladding of a breached fuel rod can be given any credit as an effective barrier to radionuclide release, is described in this test plan. 8 references, 2 figures, 4 tables

Test plan for preparing the Rapid Transuranic Monitoring Laboratory for field deployment

International Nuclear Information System (INIS)

McIsaac, C.V.; Sill, C.W.; Gehrke, R.J.; Killian, E.W.; Watts, K.D.

1994-04-01

This plan describes experimental work that will be performed during fiscal year 1994 to prepare the Rapid Transuranic Monitoring Laboratory (RTML) for routine field use by US Department of Energy (DOE) Environmental Restoration and Waste Management programs. The RTML is a mobile, field-deployable laboratory developed at the Idaho National Engineering Laboratory (INEL) that provides a rapid, cost-effective means of characterizing and monitoring radioactive waste remediation sites for low-level radioactive contaminants. Analytical instruments currently installed in the RTML include an extended-range, germanium photon analysis spectrometer with an automatic sample changer; two, large-area, ionization chamber alpha spectrometers; and four alpha continuous air monitors. The RTML was field tested at the INEL during June 1993 in conjunction with the Buried Waste Integrated Demonstration's remote retrieval demonstration. The major tasks described in this test plan are to (a) evaluate the beta detectors for use in screening soil samples for 90 Sr, (b) upgrade the alpha spectral analysis software programs, and (c) upgrade the photon spectral analysis software programs

Failure-censored accelerated life test sampling plans for Weibull distribution under expected test time constraint

International Nuclear Information System (INIS)

Bai, D.S.; Chun, Y.R.; Kim, J.G.

1995-01-01

This paper considers the design of life-test sampling plans based on failure-censored accelerated life tests. The lifetime distribution of products is assumed to be Weibull with a scale parameter that is a log linear function of a (possibly transformed) stress. Two levels of stress higher than the use condition stress, high and low, are used. Sampling plans with equal expected test times at high and low test stresses which satisfy the producer's and consumer's risk requirements and minimize the asymptotic variance of the test statistic used to decide lot acceptability are obtained. The properties of the proposed life-test sampling plans are investigated

DEEP VADOSE ZONE TREATABILITY TEST PLAN

International Nuclear Information System (INIS)

Chronister, G.B.; Truex, M.J.

2009-01-01

(sm b ullet) Treatability test plan published in 2008 (sm b ullet) Outlines technology treatability activities for evaluating application of in situ technologies and surface barriers to deep vadose zone contamination (technetium and uranium) (sm b ullet) Key elements - Desiccation testing - Testing of gas-delivered reactants for in situ treatment of uranium - Evaluating surface barrier application to deep vadose zone - Evaluating in situ grouting and soil flushing

Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca

International Nuclear Information System (INIS)

Novakovic, M.

1961-12-01

The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO 2 with beryllium cladding, cooled by CO 2 under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO 2 . This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment

Test plan for dig-face characterization performance testing

International Nuclear Information System (INIS)

Josten, N.E.

1993-09-01

The dig-face characterization concept has been under development at the Idaho National Engineering Laboratory (INEL) since FY 1992 through the support of the Buried Waste Integrated Demonstration Program. A Dig-face Characterization System conducts continuous subsurface characterization simultaneously with retrieval of hazardous and radioactive waste from buried waste sites. The system deploys multiple sensors at the retrieval operation dig-face and collects data that provide a basis for detecting, locating, and identifying hazardous conditions before they are disturbed by the retrieval equipment. This test plan describes initial efforts to test the dig-face characterization concept at the INEL Cold Test Pit using a simplified prototype apparatus and off-the-shelf sensors. The Cold Test Pit is a simulated waste site containing hazardous and radioactive waste surrogates at known locations. Testing will be directed toward three generic characterization problems: metal detection, plume detection, and radioactive source detection. The prototype apparatus will gather data using magnetometers, a ground conductivity meter, a trace gas analyzer, and a gamma ray sensor during simulated retrieval of the surrogate waste materials. The data acquired by a dig-face characterization system are unique because of the high precision, high data density, and multiple viewpoints attainable through the dig-face deployment approach. The test plan establishes procedures for collecting and validating a representative dig-face characterization data set. Analysis of these data will focus on developing criteria for predicting the depth, location, composition, and other characteristics of the surrogate waste materials. If successful, this proof-of-concept exercise will provide a foundation for future development of a fully-operational system that is capable of operating on an actual waste site

An experimental test plan for the characterization of molten salt thermochemical properties in heat transport systems

International Nuclear Information System (INIS)

Calderoni, Pattrick

2010-01-01

Molten salts are considered within the Very High Temperature Reactor program as heat transfer media because of their intrinsically favorable thermo-physical properties at temperatures starting from 300 C and extending up to 1200 C. In this context two main applications of molten salt are considered, both involving fluoride-based materials: as primary coolants for a heterogeneous fuel reactor core and as secondary heat transport medium to a helium power cycle for electricity generation or other processing plants, such as hydrogen production. The reference design concept here considered is the Advanced High Temperature Reactor (AHTR), which is a large passively safe reactor that uses solid graphite-matrix coated-particle fuel (similar to that used in gas-cooled reactors) and a molten salt primary and secondary coolant with peak temperatures between 700 and 1000 C, depending upon the application. However, the considerations included in this report apply to any high temperature system employing fluoride salts as heat transfer fluid, including intermediate heat exchangers for gas-cooled reactor concepts and homogeneous molten salt concepts, and extending also to fast reactors, accelerator-driven systems and fusion energy systems. The purpose of this report is to identify the technical issues related to the thermo-physical and thermo-chemical properties of the molten salts that would require experimental characterization in order to proceed with a credible design of heat transfer systems and their subsequent safety evaluation and licensing. In particular, the report outlines an experimental R and D test plan that would have to be incorporated as part of the design and operation of an engineering scaled facility aimed at validating molten salt heat transfer components, such as Intermediate Heat Exchangers. This report builds on a previous review of thermo-physical properties and thermo-chemical characteristics of candidate molten salt coolants that was generated as part

An experimental test plan for the characterization of molten salt thermochemical properties in heat transport systems

Energy Technology Data Exchange (ETDEWEB)

Pattrick Calderoni

2010-09-01

Molten salts are considered within the Very High Temperature Reactor program as heat transfer media because of their intrinsically favorable thermo-physical properties at temperatures starting from 300 C and extending up to 1200 C. In this context two main applications of molten salt are considered, both involving fluoride-based materials: as primary coolants for a heterogeneous fuel reactor core and as secondary heat transport medium to a helium power cycle for electricity generation or other processing plants, such as hydrogen production. The reference design concept here considered is the Advanced High Temperature Reactor (AHTR), which is a large passively safe reactor that uses solid graphite-matrix coated-particle fuel (similar to that used in gas-cooled reactors) and a molten salt primary and secondary coolant with peak temperatures between 700 and 1000 C, depending upon the application. However, the considerations included in this report apply to any high temperature system employing fluoride salts as heat transfer fluid, including intermediate heat exchangers for gas-cooled reactor concepts and homogenous molten salt concepts, and extending also to fast reactors, accelerator-driven systems and fusion energy systems. The purpose of this report is to identify the technical issues related to the thermo-physical and thermo-chemical properties of the molten salts that would require experimental characterization in order to proceed with a credible design of heat transfer systems and their subsequent safety evaluation and licensing. In particular, the report outlines an experimental R&D test plan that would have to be incorporated as part of the design and operation of an engineering scaled facility aimed at validating molten salt heat transfer components, such as Intermediate Heat Exchangers. This report builds on a previous review of thermo-physical properties and thermo-chemical characteristics of candidate molten salt coolants that was generated as part of the

Gallium-cladding compatibility testing plan: Phase 3: Test plan for centrally heated surrogate rodlet test. Revision 2

International Nuclear Information System (INIS)

Morris, R.N.; Baldwin, C.A.; Wilson, D.F.

1998-07-01

The Fissile Materials Disposition Program (FMDP) is investigating the use of weapons grade plutonium in mixed oxide (MOX) fuel for light-water reactors (LWR). Commercial MOX fuel has been successfully used in overseas reactors for many years; however, weapons derived fuel may differ from the previous commercial fuels because of small amounts of gallium impurities. A concern presently exists that the gallium may migrate out of the fuel, react with and weaken the clad, and thereby promote loss of fuel pin integrity. Phases 1 and 2 of the gallium task are presently underway to investigate the types of reactions that occur between gallium and clad materials. This is a Level-2 document as defined in the Fissile Materials Disposition Program Light-Water Reactor Mixed-Oxide Fuel Irradiation Test Project Plan. This Plan summarizes the projected Phase 3 Gallium-Cladding compatibility heating test and the follow-on post test examination (PTE). This work will be performed using centrally-heated surrogate pellets, to avoid unnecessary complexities and costs associated with working with plutonium and an irradiation environment. Two sets of rodlets containing pellets prepared by two different methods will be heated. Both sets will have an initial bulk gallium content of approximately 10 ppm. The major emphasis of the PTE task will be to examine the material interactions, particularly indications of gallium transport from the pellets to the clad

Report of experimental hall subworking group

International Nuclear Information System (INIS)

Miyake, K.; Ohama, T.; Takahashi, K.

1982-01-01

The general plan of constructing the TRISTAN e + e - colliding beam experimental halls may be divided into two parts. The first step is to construct two test-experimental halls associated with the 6.5 GeV x 6.5 GeV e + e - accumulator ring, and the second step is to build four experimental halls at the 30 GeV x 30 GeV e + e - TRISTAN main ring. At this workshop, extensive discussions on the detailed design of the four main ring experimental halls have been made. Four experimental areas will be built at the main ring, and two test-experimental halls at the accumulating ring. Among the four areas at the main ring, two will be used for electron-proton possible as well as electron-positron colliding beam experiment. The other two will be used exclusively for e + e - colliding experiments. Only a preliminary design has been made for these four experimental areas. A tentative plan of a larger experimental hall includes a counting and data processing room, a utility room, and a radiation safety control room. Two smaller halls have simpler structure. The figures of the experimental halls are presented. The two test-experimental halls at the accumulator ring will be used to test the detectors for e + e - colliding experiments before the final installation. The utility rooms designed for the halls are used to supply coolant and electric power of superconducting magnets. At the workshop, various ideas concerning the preliminary plan are presented. (Kato, T.)

Advanced Stirling Convertor Durability Testing: Plans and Interim Results

Science.gov (United States)

Meer, David W.; Oriti, Salvatore M.

2012-01-01

The U.S. Department of Energy (DOE), Lockheed Martin Corporation (LM), and NASA Glenn Research Center (GRC) have been developing the Advanced Stirling Radioisotope Generator (ASRG) for use as a power system for space science missions. In support of this program, GRC has been involved in testing Stirling convertors, including the Advanced Stirling Convertor (ASC), for use in the ASRG. This testing includes electromagnetic interference/compatibility (EMI/EMC), structural dynamics, advanced materials, organics, and unattended extended operation. The purpose of the durability tests is to experimentally demonstrate the margins in the ASC design. Due to the high value of the hardware, previous ASC tests focused on establishing baseline performance of the convertors within the nominal operating conditions. The durability tests present the first planned extension of the operating conditions into regions beyond those intended to meet the product spec, where the possibility exists of lateral contact, overstroke, or over-temperature events. These tests are not intended to cause damage that would shorten the life of the convertors, so they can transition into extended operation at the conclusion of the tests. This paper describes the four tests included in the durability test sequence: 1) start/stop cycling, 2) exposure to constant acceleration in the lateral and axial directions, 3) random vibration at increased piston amplitude to induce contact events, and 4) overstroke testing to simulate potential failures during processing or during the mission life where contact events could occur. The paper also summarizes the analysis and simulation used to predict the results of each of these tests.

Test plan for the field evaluation and demonstration of the Contamination Control Unit

International Nuclear Information System (INIS)

Winberg, M.R.; Thompson, D.N.

1993-06-01

This report describes test details of a full demonstration of the Contamination Control Unit (CCU). The CCU is a mobile trailer capable of employing the use of soil fixatives, dust suppression agents, misting, and vacuum systems. These systems can perform a large number of contamination control functions to support the Office of Waste Technology Development (OTD) Buried Waste Integrated Demonstration (BWID) projects, transuranic (TRU) waste retrieval operations, and emergency response for hazardous and radioactive materials incidents. The demonstration will include both performance testing at the North Holmes Laboratory Facility (NHLF) and field testing in conjunction with the Remote Excavation System Demonstration at the Cold Test Pit. The NHLF will test operational parameters using water only, and the field demonstration at the Cold Test Pit involves full scale operation of vacuum, fixant, misting, and dust suppression systems. Test objectives, detailed experimental procedures, and data quality objectives necessary to perform the field demonstration are included in this test plan

Integrated Program of Experimental Diagnostics at the NNSS: An Integrated, Prioritized Work Plan for Diagnostic Development and Maintenance and Supporting Capability

International Nuclear Information System (INIS)

2010-01-01

This Integrated Program of Experimental Diagnostics at the NNSS is an integrated prioritized work plan for the Nevada National Security Site (NNSS), formerly the Nevada Test Site (NTS), program that is independent of individual National Security Enterprise Laboratories (Labs) requests or specific Subprograms being supported. This prioritized work plan is influenced by national priorities presented in the Predictive Capability Framework (PCF) and other strategy documents (Primary and Secondary Assessment Technologies Plans and the Plutonium Experiments Plan). This document satisfies completion criteria for FY 2010 MRT milestone No.3496: Document an integrated, prioritized work plan for diagnostic development, maintenance, and supporting capability. This document is an update of the 3-year NNSS plan written a year ago, September 21, 2009, to define and understand Lab requests for diagnostic implementation. This plan is consistent with Lab interpretations of the PCF, Primary Assessment Technologies, and Plutonium Experiment plans.

Plan Merging : Experimental results

NARCIS (Netherlands)

De Weerdt, M.M.; Van der Krogt, R.P.J.; Zutt, J.

2003-01-01

In this paper we discuss the results of a plan merging algorithm. This algorithm coordinates the plans of multiple, autonomous agents, each able to independently find a plan. This algorithm is evaluated using realistic data from a taxi company. We show that when we allow passengers to be a few

Initial Efficacy Testing of an Autobiographical Memory Intervention on Advance Care Planning for Patients With Terminal Cancer.

Science.gov (United States)

Brohard, Cheryl

2017-11-01

To test the efficacy of a novel intervention to facilitate advance care planning.
. Exploratory, quasiexperimental pilot study with two independent groups.
. A large hospice located in the southwestern United States. 
. A convenience sample of 50 participants with terminal cancer enrolled in hospice.
. An autobiographical memory (ABM) intervention used the participants' experiences with cancer and end of life for the purpose of directing advance care planning.
. Two domains of advance care planning, decision making and communication, were measured in relation to 11 variables. The ABM intervention was nonthreatening, short in duration, and easily completed with participants as they recalled, without hesitation, specific personal memories of family and friends who had died and their advance care plans. The Mann-Whitney nonparametric test revealed that participants in the experimental group had a higher average rank than those in the control group for communicating the decision about antibiotics, as well as exhibited a trend toward significance for five other advance care planning variables.
. Findings showed that directive ABMs may be effective in influencing the decision making and communication of advance care planning for terminally ill patients with cancer.
. The current level of understanding about using the ABM intervention suggests that nurses can initiate an advance care planning conversation using this approach.

Development of quality assurance and performance testing for the Process Experimental Pilot Plant

International Nuclear Information System (INIS)

Dole, L.R.; McDaniel, E.W.; Robinson, S.M.

1984-08-01

The Process Experimental Pilot Plant (PREPP) is planned for operation by EG and G Idaho, Inc., to demonstrate a full-scale, cement-based, disposal process for transuranic (TRU) wastes. Procedures need to be developed to determine the quality of the waste product during processing and the durability of the final waste form produced in this facility. This report summarizes basic guidelines for the selection of the waste form composition and process conditions that affect product performance. Physical property tests that may be applicable for quality assurance during processing are also described. Approaches to accelerated performance tests needed to predict the performance of the cement-based waste form are identified, and suggestions are made for the development of processing tests to ensure the quality of the final waste-host product. 29 references, 3 figures, 4 tables

Development of quality assurance and performance testing for the Process Experimental Pilot Plant

International Nuclear Information System (INIS)

Dole, L.R.; McDaniel, E.W.; Robinson, S.M.

1984-06-01

The Process Experimental Pilot Plant (PREPP) is planned for operation by EG and G Idaho, Inc., to demonstrate a full-scale, cement-based, disposal process for transuranic (TRU) wastes. Procedures need to be developed to determine the quality of the waste product during processing and the durability of the final waste form produced in this facility. This report summarizes basic guidelines for the selection of the waste form composition and process conditions that affect product performance. Physical property tests that may be applicable for quality assurance during processing are also described. Approaches to accelerated performance tests needed to predict the performance of the cement-based waste form are identified, and suggestions are made for the development of processing tests to assure the quality of the final waste-host product. 29 references, 3 figures, 3 tables

Experimental Plan for Crystal Accumulation Studies in the WTP Melter Riser

Energy Technology Data Exchange (ETDEWEB)

Miller, D. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL); Fowley, M. [Savannah River Site (SRS), Aiken, SC (United States). Savannah River National Lab. (SRNL)

2015-04-28

This experimental plan defines crystal settling experiments to be in support of the U.S. Department of Energy – Office of River Protection crystal tolerant glass program. The road map for development of crystal-tolerant high level waste glasses recommends that fluid dynamic modeling be used to better understand the accumulation of crystals in the melter riser and mechanisms of removal. A full-scale version of the Hanford Waste Treatment and Immobilization Plant (WTP) melter riser constructed with transparent material will be used to provide data in support of model development. The system will also provide a platform to demonstrate mitigation or recovery strategies in off-normal events where crystal accumulation impedes melter operation. Test conditions and material properties will be chosen to provide results over a variety of parameters, which can be used to guide validation experiments with the Research Scale Melter at the Pacific Northwest National Laboratory, and that will ultimately lead to the development of a process control strategy for the full scale WTP melter. The experiments described in this plan are divided into two phases. Bench scale tests will be used in Phase 1 (using the appropriate solid and fluid simulants to represent molten glass and spinel crystals) to verify the detection methods and analytical measurements prior to their use in a larger scale system. In Phase 2, a full scale, room temperature mockup of the WTP melter riser will be fabricated. The mockup will provide dynamic measurements of flow conditions, including resistance to pouring, as well as allow visual observation of crystal accumulation behavior.

Windows Calorimeter Control (WinCal) program computer software test plan

International Nuclear Information System (INIS)

Pertzborn, N.F.

1997-01-01

This document provides the information and guidelines necessary to conduct all the required testing of the Windows Calorimeter Control (WinCal) system. The strategy and essential components for testing the WinCal System Project are described in this test plan. The purpose of this test plan is to provide the customer and performing organizations with specific procedures for testing the specified system's functions

Configuration management plan for Machine Interface Test System (MITS)

International Nuclear Information System (INIS)

O'Neill, C.K.

1980-01-01

The discipline required by this plan will apply from the establishment of a configuration baseline until completion of the final test in the MITS. The plan applies to configured items of hardware and software as well as to the specifications and drawings for these items. The plan encompasses establishment of the facility baseline, interface definition, classes of change, change control, change paper, organizational responsibilities and relationships, test configuration (as opposed to facility), and configuration data retention

LERF Basin 44 Process Test Plan

International Nuclear Information System (INIS)

LUECK, K.J.

1999-01-01

This document presents a plan to process a portion of the Liquid Effluent Retention Facility (LERF) Basin 44 wastewater through the 200 Area Effluent Treatment Facility (ETF). The objective of this process test is to determine the most effective/efficient method to treat the wastewater currently stored in LERF Basin 44. The process test will determine the operational parameters necessary to comply with facility effluent discharge permit limits (Ecology 1995) and the Environmental Restoration Disposal Facility (ERDF) acceptance criteria (BHI-00139), while achieving ALARA goals and maintaining the integrity of facility equipment. A major focus of the test plan centers on control of contamination due to leaks and/or facility maintenance. As a pre-startup item, all known leaks will be fixed before the start of the test. During the course of the test, a variety of contamination control measures will be evaluated for implementation during the treatment of the remaining Basin 44 inventory. Of special interest will be techniques and tools used to prevent contamination spread during sampling and when opening contaminated facility equipment/piping. At the conclusion of the test, a post ALARA review will be performed to identify lessons learned from the test run which can be applied to the treatment of the remaining Basin 44 inventory. The volume of wastewater to be treated during this test run is 500,000 gallons. This volume limit is necessary to maintain the ETF radiological inventory limits per the approved authorization basis. The duration of the process test is approximately 30 days

Surface-based test plan, Deaf Smith County, Texas Site: Draft

International Nuclear Information System (INIS)

1985-01-01

The Surface-Based Test Plan (SBTP) is the plan which accounts for all surface-based site field work to be conducted at the Permian salt site selected for characterization. The SBTP relates data needs from program requirement documents and presents plans to satisfy the data needs. The SBTP excludes plans for construction of the Exploratory Shaft Facility (ESF) and plans for the in situ testing. The SBTP is a hierarchical plan stemming from the Technical Program Plan. The SBTP describes in detail the process by which surface-based study plans are defined, developed, and controlled. The plans hierarchy extends downward thru subordinate Site Study Plans (SSPs), which describe in detail elements of field work to be done, to detailed Procedures which document the exact methodologies to be employed in the conduct of field work. The plan is a QA level S document, although some of its elements are at lower QA levels. The plan is a controlled document, and any proposed amendments to the plan or subordinate documents can only be implemented through the specified change control procedure

Phased Startup Initiative Phases 3 and 4 Test Plan and Test Specification (OCRWM)

International Nuclear Information System (INIS)

PITNER, A.L.

2000-01-01

Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. These tests are described in separate planning documents. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: (1) Define the test scope for the FRS and IWTS; (2) Provide detailed test requirements that can be used to write the specific test procedures; (3) Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and (4) Define specific test objectives and acceptance criteria

Pre-irradiation testing of experimental fuel elements

International Nuclear Information System (INIS)

Basova, B.G.; Davydov, E.F.; Dvoretskij, V.G.; Ivanov, V.B.; Syuzev, V.N.; Timofeev, G.A.; Tsykanov, V.A.

1979-01-01

The problems of testing of experimental fuel elements of nuclear reactors on the basis of complex accountancy of the factors defining operating capacity of the fuel elements are considered. The classification of the parameters under control and the methods of initial technological testing, including testing of the fuel product, cladding and fished fuel element, is given. The requirements to the apparatus used for complex testing are formulated. One of the possible variants of representation of the information obtained in the form of the input certificate of a single fuel element under study is proposed. The processing flowsheet of the gathered information using the computer is given. The approach under consideration is a methodological basis of investigation of fuel element operating life at the testing stage of the experimental fuel elements

Experimental tests of quantum chromodynamics

International Nuclear Information System (INIS)

Dorfan, J.

1987-04-01

Experimental tests of quantum chromodynamics are discussed in the e + e - continuum, in pp and anti p p collisions, in measurements of α/sub s/ from Υ decays, in deep inelastic lepton scattering, and in the measurement of the photon structure function. A large body of data relating to the testing of quantum chromodynamics is reviewed, showing qualitative agreement between the data from a wide range of processes and QCD. 66 refs., 79 figs

Test plan for glove box testing with the real-time transuranic dust monitor

International Nuclear Information System (INIS)

Partin, J.K.; Fincke, J.R.

1994-10-01

This test plan describes the objectives, instrumentation, and testing procedures used to prove the feasibility of a real-time transuranic dust monitor (RTDM). The RTDM is under development at the Idaho National Engineering Laboratory (INEL) as a Waste Characterization Technology funded by the Buried Waste Integrated Demonstration Project. The instrument is an in situ monitor that uses optical techniques to establish particle size, particle number density, and mass and species of heavy metal contamination. US Department of Energy orders mandate the assessment of radiological exposure and contamination spread during the remediation of radioactive waste. Of particular concern is heavy metal contamination of dust, both radioactive and nonradioactive. Small particles of metal, particularly the radioactive species, tend to become electrically charged and consequently attach themselves to dust particles. This airborne activated dust is a primary means of contamination transport during remediation activities, and therefore, must be continuously monitored to protect personnel involved in the operations and to control the spread of contamination. If real-time monitoring is not available there is increased likelihood of generating unacceptably high levels of contamination and being forced to shut down costly retrieval operations to decontaminate. A series of experiments are described to determine the optimal experimental design, operational parameters, and levels of detection for the RTDM. Initial screening will be performed using monodisperse particle standards to set parameters and calibrate the instrument. Additional testing will be performed using INEL soil samples spiked with a surrogate, cerium oxide, to prove the design before transporting the apparatus to the Test Reactor Area for testing with plutonium-contaminated dusts

Geochemical Testing And Model Development - Residual Tank Waste Test Plan

International Nuclear Information System (INIS)

Cantrell, K.J.; Connelly, M.P.

2010-01-01

This Test Plan describes the testing and chemical analyses release rate studies on tank residual samples collected following the retrieval of waste from the tank. This work will provide the data required to develop a contaminant release model for the tank residuals from both sludge and salt cake single-shell tanks. The data are intended for use in the long-term performance assessment and conceptual model development.

Experimental validation of a new heterogeneous mechanical test design

Science.gov (United States)

Aquino, J.; Campos, A. Andrade; Souto, N.; Thuillier, S.

2018-05-01

Standard material parameters identification strategies generally use an extensive number of classical tests for collecting the required experimental data. However, a great effort has been made recently by the scientific and industrial communities to support this experimental database on heterogeneous tests. These tests can provide richer information on the material behavior allowing the identification of a more complete set of material parameters. This is a result of the recent development of full-field measurements techniques, like digital image correlation (DIC), that can capture the heterogeneous deformation fields on the specimen surface during the test. Recently, new specimen geometries were designed to enhance the richness of the strain field and capture supplementary strain states. The butterfly specimen is an example of these new geometries, designed through a numerical optimization procedure where an indicator capable of evaluating the heterogeneity and the richness of strain information. However, no experimental validation was yet performed. The aim of this work is to experimentally validate the heterogeneous butterfly mechanical test in the parameter identification framework. For this aim, DIC technique and a Finite Element Model Up-date inverse strategy are used together for the parameter identification of a DC04 steel, as well as the calculation of the indicator. The experimental tests are carried out in a universal testing machine with the ARAMIS measuring system to provide the strain states on the specimen surface. The identification strategy is accomplished with the data obtained from the experimental tests and the results are compared to a reference numerical solution.

Critical considerations when planning experimental in vivo studies in dental traumatology

DEFF Research Database (Denmark)

Andreasen, Jens O; Andersson, Lars

2011-01-01

In vivo studies are sometimes needed to understand healing processes after trauma. For several reasons, not the least ethical, such studies have to be carefully planned and important considerations have to be taken into account about suitability of the experimental model, sample size and optimizing...

Light Duty Utility Arm Software Test Plan

International Nuclear Information System (INIS)

Kiebel, G.R.

1995-01-01

This plan describes how validation testing of the software will be implemented for the integrated control and data acquisition system of the Light Duty Utility Arm System (LDUA). The purpose of LDUA software validation testing is to demonstrate and document that the LDUA software meets its software requirements specification

INEL test plan for evaluating waste assay systems

International Nuclear Information System (INIS)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP

In situ vitrification laboratory-scale test work plan

International Nuclear Information System (INIS)

Nagata, P.K.; Smith, N.L.

1991-05-01

The Buried Waste Program was established in October 1987 to accelerate the studies needed to develop a long-term management plan for the buried mixed waste at the Radioactive Waste Management Complex at Idaho Engineering Laboratory. The In Situ Vitrification Project is being conducted in a Comprehensive Environmental Response, Compensation, and Liability Act feasibility study format to identify methods for the long-term management of mixed buried waste. To support the overall feasibility study, the situ vitrification treatability investigations are proceeding along the three parallel paths: laboratory-scale tests, intermediate field tests, and field tests. Laboratory-scale tests are being performed to provide data to mathematical modeling efforts, which, in turn, will support design of the field tests and to the health and safety risk assessment. This laboratory-scale test work plan provides overall testing program direction to meet the current goals and objectives of the in situ vitrification treatability investigation. 12 refs., 1 fig., 7 tabs

INEL test plan for evaluating waste assay systems

Energy Technology Data Exchange (ETDEWEB)

Mandler, J.W.; Becker, G.K.; Harker, Y.D.; Menkhaus, D.E.; Clements, T.L. Jr.

1996-09-01

A test bed is being established at the Idaho National Engineering Laboratory (INEL) Radioactive Waste Management Complex (RWMC). These tests are currently focused on mobile or portable radioassay systems. Prior to disposal of TRU waste at the Waste Isolation Pilot Plant (WIPP), radioassay measurements must meet the quality assurance objectives of the TRU Waste Characterization Quality Assurance Program Plan. This test plan provides technology holders with the opportunity to assess radioassay system performance through a three-tiered test program that consists of: (a) evaluations using non-interfering matrices, (b) surrogate drums with contents that resemble the attributes of INEL-specific waste forms, and (c) real waste tests. Qualified sources containing a known mixture and range of radionuclides will be used for the non-interfering and surrogate waste tests. The results of these tests will provide technology holders with information concerning radioassay system performance and provide the INEL with data useful for making decisions concerning alternative or improved radioassay systems that could support disposal of waste at WIPP.

Remotely Piloted Vehicles for Experimental Flight Control Testing

Science.gov (United States)

Motter, Mark A.; High, James W.

2009-01-01

A successful flight test and training campaign of the NASA Flying Controls Testbed was conducted at Naval Outlying Field, Webster Field, MD during 2008. Both the prop and jet-powered versions of the subscale, remotely piloted testbeds were used to test representative experimental flight controllers. These testbeds were developed by the Subsonic Fixed Wing Project s emphasis on new flight test techniques. The Subsonic Fixed Wing Project is under the Fundamental Aeronautics Program of NASA's Aeronautics Research Mission Directorate (ARMD). The purpose of these testbeds is to quickly and inexpensively evaluate advanced concepts and experimental flight controls, with applications to adaptive control, system identification, novel control effectors, correlation of subscale flight tests with wind tunnel results, and autonomous operations. Flight tests and operator training were conducted during four separate series of tests during April, May, June and August 2008. Experimental controllers were engaged and disengaged during fully autonomous flight in the designated test area. Flaps and landing gear were deployed by commands from the ground control station as unanticipated disturbances. The flight tests were performed NASA personnel with support from the Maritime Unmanned Development and Operations (MUDO) team of the Naval Air Warfare Center, Aircraft Division

A Test Platform for Planned Field Operations Using LEGO Mindstorms NXT

Directory of Open Access Journals (Sweden)

Gareth Edwards

2013-11-01

Full Text Available Testing agricultural operations and management practices associated with different machinery, systems and planning approaches can be both costly and time-consuming. Computer simulations of such systems are used for development and testing; however, to gain the experience of real-world performance, an intermediate step between simulation and full-scale testing should be included. In this paper, a potential common framework using the LEGO Mindstorms NXT micro-tractor platform is described in terms of its hardware and software components. The performance of the platform is demonstrated and tested in terms of its capability of supporting decision making on infield operation planning. The proposed system represents the basic measures for developing a complete test platform for field operations, where route plans, mission plans, multiple-machinery cooperation strategies and machinery coordination can be executed and tested in the laboratory.

Safety demonstration test (SR-1/S1C-1) plan of HTTR (Contract research)

Energy Technology Data Exchange (ETDEWEB)

Nakagawa, Shigeaki; Sakaba, Nariaki; Takada, Eiji; Tachibana, Yukio; Saito, Kenji; Furusawa, Takayuki; Sawa, Kazuhiro [Japan Atomic Energy Research Inst., Oarai, Ibaraki (Japan). Oarai Research Establishment

2003-03-01

Safety demonstration tests in the HTTR (High Temperature Engineering Test Reactor) will be carried out in order to verify inherent safety features of the HTGR (High Temperature Gas-cooled Reactor). The first phase of the safety demonstration tests includes the reactivity insertion test by the control rod withdrawal and the coolant flow reduction test by the circulator trip. In the second phase, accident simulation tests will be conducted. By comparison of their experimental and analytical results, the prediction capability of the safety evaluation codes such as the core and the plant dynamics codes will be improved and verified, which will contribute to establish the safety design and the safety evaluation technologies of the HTGRs. The results obtained through its safety demonstration tests will be also utilised for the establishment of the safety design guideline, the safety evaluation guideline, etc. This paper describes the test program of the overall safety demonstration tests and the test method, the test conditions and the results of the pre-test analysis of the reactivity insertion test and the partial gas circulator trip test planned in March 2003. (author)

Performance Demonstration Program Plan for the WIPP Experimental-Waste Characterization Program

International Nuclear Information System (INIS)

1991-02-01

The Performance Demonstration Program is designed to ensure that compliance with the Quality Assurance Objective, identified in the Quality Assurance Program Plan for the WIPP Experimental-Waste Characterization Program (QAPP), is achieved. This Program Plan is intended for use by the WPO to assess the laboratory support provided for the characterization of WIPP TRU waste by the storage/generator sites. Phase 0 of the Performance Demonstration Program encompasses the analysis of headspace gas samples for inorganic and organic components. The WPO will ensure the implementation of this plan by designating an independent organization to coordinate and provide technical oversight for the program (Program Coordinator). Initial program support, regarding the technical oversight and coordination functions, shall be provided by the USEPA-ORP. This plan identifies the criteria that will be used for the evaluation of laboratory performance, the responsibilities of the Program Coordinator, and the responsibilities of the participating laboratories. 5 tabs

Los Alamos Experimental Engineering Waste Burial Facility: design considerations and preliminary experimental plan

International Nuclear Information System (INIS)

DePoorter, G.L.

1981-01-01

The Experimental Engineered Waste Burial Facility is a field test site where generic experiments can be performed on several scales to get the basic information necessary to understand the processes occurring in low-level waste disposal facilities. The experiments include hydrological, chemical, mechanical, and biological factors. In order to separate these various factors in the experiments and to extrapolate the experimental results to actual facilities, experiments will be performed on several different scales

NASA's Plan for SDLS Testing

Science.gov (United States)

Bailey, Brandon

2015-01-01

The Space Data Link Security (SDLS) Protocol is a Consultative Committee for Space Data Systems (CCSDS) standard which extends the known Data Link protocols to secure data being sent over a space link by providing confidentiality and integrity services. This plan outlines the approach by National Aeronautics Space Administration (NASA) in performing testing of the SDLS protocol using a prototype based on an existing NASA missions simulator.

100 Area excavation treatability test plan

International Nuclear Information System (INIS)

1993-08-01

This test plan documents the requirements for a treatability study on field radionuclide analysis and dust control techniques. These systems will be used during remedial actions involving excavation. The data from this treatability study will be used to support the feasibility study (FS) process. Excavation is one of the high-priority, near-term, treatability study needs identified in the program plan (DOE-RL 1992f). Excavation of contaminated soils and buried solid wastes is included in several of the alternatives identified in the 100 Area FS. Although a common activity, excavation has only been used occasionally at the Hanford Site for waste removal applications. The most recent applications are excavation of the 618-9 burial ground and partial remediation of the 316-5 process trenches (DOE-RL 1992a, 1992b). Both projects included excavation of soil and dust control (using water sprays). Excavation is a well-developed technology and equipment is readily available; however, certain aspects of the excavation process require testing before use in full-scale operations. These include the following: Measurement and control of excavation-generated dust and airborne contamination; verification of field analytical system capabilities; demonstration of soil removal techniques specific to the 100 Area waste site types and configurations. The execution of this treatability test may produce up to 500 yd 3 of contaminated soil, which will be used for future treatability tests. These tests may include soil washing with vitrification of the soil washing residuals. Other tests will be conducted if soil washing is not a viable alternative

Standard review plan for the review and evaluation of emergency plans for research and test reactors

International Nuclear Information System (INIS)

1983-10-01

This document provides a Standard Review Plan to assure that complete and uniform reviews are made of research and test reactor radiological emergency plans. The report is organized under ten planning standards which correspond to the guidance criteria in American National Standard ANSI/ANS 15.16 - 1982 as endorsed by Revision 1 to Regulatory Guide 2.6. The applicability of the items under each planning standard is indicated by subdivisions of the steady-state thermal power levels at which the reactors are licensed to operate. Standard emergency classes and example action levels for research and test reactors which should initiate these classes are given in an Appendix. The content of the emergency plan is as follows: the emergency plan addresses the necessary provisions for coping with radiological emergencies. Activation of the emergency plan is in response to the emergency action levels. In addition to addressing those severe emergencies that will fall within one of the standard emergency classes, the plan also discusses the necessary provisions to deal with radiological emergencies of lesser severity that can occur within the operations boundary. The emergency plan allows for emergency personnel to deviate from actions described in the plan for unusual or unanticipated conditions

Experimental plan of Σp scatterings at J-PARC

Directory of Open Access Journals (Sweden)

Tamura H.

2012-02-01

Full Text Available In order to test theoretical frameworks of the baryon-baryon interactions and to confirm the ”Pauli effect between quarks” for the first time, we propose an experiment to measure low-energy hyperon proton scattering cross sections in the following channels with high statistics, 1. Σ− p elastic scattering, 2. Σ− p → Λn inelastic scattering, 3. Σ+ p elastic scattering. According to theoretical models based on quark-gluon picture for the short range part of the baryon-baryon interactions, the Σ+ p channel is expected to have an extremely repulsive core due to the Pauli effect between quarks, which leads a Σ+ p cross section twice as large as that predicted by conventional meson exchange models with a phenomenologically treated short range repulsive core. In addition, measurement of the Σ− p channel where the quark Pauli effect is not effective is also necessary to test the present theoretical models based on meson exchange picture with the flavor SU(3 symmetry. Thus this experiment will provide essential data to test the frameworks of the theoretical models of the baryon-baryon interactions and to investigate the nature of the repulsive core which has not been understood yet. In order to overcome the experimental difficulties in measuring low-energy hyperon proton scattering, we will use a new experimental technique in which a liquid H2 target is used as hyperon production and hyperon scattering targets with a detector system surrounding the LH2 target for detection of a scattered proton and a decay product from a hyperon. The hyperon scattering event is kinematically identified. Because imaging detectors used in past experiments are not employed, high intensity π beam can be used, allowing us to take high statistics data of 100 times more than the previous experiments. We have proposed an experiment of Σp scattering at the K1.8 beam line by utilizing the K1.8 beam line spectrometer and the SKS spectrometer. A high intensity �

Proposal for a strategic management plan for experimental agricultural and academic farm "El Cairo" of Arauca

Directory of Open Access Journals (Sweden)

Elías Nieves

2014-04-01

Full Text Available This paper presents a design for a strategic management plan for the Experimental Agricultural and Academic Farm: El Cairo of the Universidad Nacional de Colombia, Orinoquía branch. A non-experimental methodological design was used, from which a situational analysis of the farm was generated, which was used as a basis to formulate and design a Strategic Management plan for a five-year period. It was concluded that the current organization and management plan does not meet the mission objectives of research, teaching, and continuing education, suggesting a need for the articulation of the farm with the administrative and academic structure of the university in carrying out the strategic management plan derived from the current research.

An innovative approach for planning and execution of pre-experimental runs for Design of Experiments

Directory of Open Access Journals (Sweden)

Muhammad Arsalan Farooq

2016-09-01

Full Text Available This paper addresses the study of the pre-experimental planning phase of the Design of Experiments (DoE in order to improve the final product quality. The pre-experimental planning phase includes a clear identification of the problem statement, selection of control factors and their respective levels and ranges. To improve production quality based on the DoE a new approach for the pre-experimental planning phase, called Non-Conformity Matrix (NCM, is presented. This article also addresses the key steps of the pre-experimental runs considering a consumer goods manufacturing process. Results of the application for an industrial case show that this methodology can support a clear definition of the problem and also a correct identification of the factor ranges in particular situations. The proposed new approach allows modeling the entire manufacturing system holistically and correctly defining the factor ranges and respective levels for a more effective application of DoE. This new approach can be a useful resource for both research and industrial practitioners who are dedicated to large DoE projects with unknown factor interactions, when the operational levels and ranges are not completely defined.

Experimental dosimetry in conformal breast teletherapy compared with the planning system

International Nuclear Information System (INIS)

Nogueira, Luciana Batista; Silva, Hugo Leonardo Lemos; Passos Ribeiro de Campos, Tarcísio

2015-01-01

The objective of this study was to compare and analyse the absorbed dose profiles from the conformal radiotherapy planning and experimental dosimetry taken in a breast anthropomorphic and anthropometric phantom. Conformal radiotherapy planning was elaborated in the Treatment Planning System (TPS). EBT2 Gafchromic radiochromic films were applied as dosimeters, positioned internally and superficially in the breast phantom. The standard radiation protocol was applied in the breast phantom. The films were digitalised, and their responses were analysed in RGB. The optical densities were processed, reproducing the spatial dose distribution. - Highlights: • Distributions of absorbed doses were generated by the TPS and measured by radiochromic films. • The breast phantom simulated a human breast in position for treatment. • A large portion of the glandular tissue absorbed doses that were equivalent to the radiotherapy planning. • There were regions of hot spots and small areas of under dosage in deeper areas at the lung interface

Tests to Help Plan Opportunity Moves

Science.gov (United States)

2005-01-01

Rover engineers check how a test rover moves in material chosen to simulate some difficult Mars driving conditions. The scene is inside the In-Situ Instrument Laboratory at NASA's Jet Propulsion Laboratory, Pasadena, Calif. These tests in early May 2005 were designed to help plan the best way for the rover Opportunity to drive off of a soft-sand dune that the rover dug itself into the previous week. The mixture of sandy and powdery material brought in for these specific tests matched the way the soil underneath Opportunity caked onto wheels, filling the spaces between the cleats on the wheels.

High Burnup Dry Storage Cask Research and Development Project, Final Test Plan

Energy Technology Data Exchange (ETDEWEB)

None

2014-02-27

EPRI is leading a project team to develop and implement the first five years of a Test Plan to collect data from a SNF dry storage system containing high burnup fuel.12 The Test Plan defined in this document outlines the data to be collected, and the storage system design, procedures, and licensing necessary to implement the Test Plan.13 The main goals of the proposed test are to provide confirmatory data14 for models, future SNF dry storage cask design, and to support license renewals and new licenses for ISFSIs. To provide data that is most relevant to high burnup fuel in dry storage, the design of the test storage system must mimic real conditions that high burnup SNF experiences during all stages of dry storage: loading, cask drying, inert gas backfilling, and transfer to the ISFSI for multi-year storage.15 Along with other optional modeling, SETs, and SSTs, the data collected in this Test Plan can be used to evaluate the integrity of dry storage systems and the high burnup fuel contained therein over many decades. It should be noted that the Test Plan described in this document discusses essential activities that go beyond the first five years of Test Plan implementation.16 The first five years of the Test Plan include activities up through loading the cask, initiating the data collection, and beginning the long-term storage period at the ISFSI. The Test Plan encompasses the overall project that includes activities that may not be completed until 15 or more years from now, including continued data collection, shipment of the Research Project Cask to a Fuel Examination Facility, opening the cask at the Fuel Examination Facility, and examining the high burnup fuel after the initial storage period.

Steel Fibers Reinforced Concrete Pipes - Experimental Tests and Numerical Simulation

Science.gov (United States)

Doru, Zdrenghea

2017-10-01

The paper presents in the first part a state of the art review of reinforced concrete pipes used in micro tunnelling realised through pipes jacking method and design methods for steel fibres reinforced concrete. In part two experimental tests are presented on inner pipes with diameters of 1410mm and 2200mm, and specimens (100x100x500mm) of reinforced concrete with metal fibres (35 kg / m3). In part two experimental tests are presented on pipes with inner diameters of 1410mm and 2200mm, and specimens (100x100x500mm) of reinforced concrete with steel fibres (35 kg / m3). The results obtained are analysed and are calculated residual flexural tensile strengths which characterise the post-cracking behaviour of steel fibres reinforced concrete. In the third part are presented numerical simulations of the tests of pipes and specimens. The model adopted for the pipes test was a three-dimensional model and loads considered were those obtained in experimental tests at reaching breaking forces. Tensile stresses determined were compared with mean flexural tensile strength. To validate tensile parameters of steel fibres reinforced concrete, experimental tests of the specimens were modelled with MIDAS program to reproduce the flexural breaking behaviour. To simulate post - cracking behaviour was used the method σ — ε based on the relationship stress - strain, according to RILEM TC 162-TDF. For the specimens tested were plotted F — δ diagrams, which have been superimposed for comparison with the similar diagrams of experimental tests. The comparison of experimental results with those obtained from numerical simulation leads to the following conclusions: - the maximum forces obtained by numerical calculation have higher values than the experimental values for the same tensile stresses; - forces corresponding of residual strengths have very similar values between the experimental and numerical calculations; - generally the numerical model estimates a breaking force greater

Experimental apparatus to test air trap valves

Science.gov (United States)

Lemos De Lucca, Y. de F.; de Aquino, G. A.; Filho, J. G. D.

2010-08-01

It is known that the presence of trapped air within water distribution pipes can lead to irregular operation or even damage to the distribution systems and their components. The presence of trapped air may occur while the pipes are being filled with water, or while the pumping systems are in operation. The formation of large air pockets can produce the water hammer phenomenon, the instability and the loss of pressure in the water distribution networks. As a result, it can overload the pumps, increase the consumption of electricity, and damage the pumping system. In order to avoid its formation, all of the trapped air should be removed through "air trap valves". In Brazil, manufacturers frequently have unreliable sizing charts, which cause malfunctioning of the "air trap valves". The result of these malfunctions causes accidents of substantial damage. The construction of a test facility will provide a foundation of technical information that will be used to help make decisions when designing a system of pipelines where "air trap valves" are used. To achieve this, all of the valve characteristics (geometric, mechanic, hydraulic and dynamic) should be determined. This paper aims to describe and analyze the experimental apparatus and test procedure to be used to test "air trap valves". The experimental apparatus and test facility will be located at the University of Campinas, Brazil at the College of Civil Engineering, Architecture, and Urbanism in the Hydraulics and Fluid Mechanics laboratory. The experimental apparatus will be comprised of various components (pumps, steel pipes, butterfly valves to control the discharge, flow meter and reservoirs) and instrumentation (pressure transducers, anemometer and proximity sensor). It should be emphasized that all theoretical and experimental procedures should be defined while taking into consideration flow parameters and fluid properties that influence the tests.

Experimental apparatus to test air trap valves

Energy Technology Data Exchange (ETDEWEB)

Lemos De Lucca, Y de F [CTH-DAEE-USP/FAAP/UNICAMP (Brazil); Aquino, G A de [SABESP/UNICAMP (Brazil); Filho, J G D, E-mail: yvone.lucca@gmail.co [Water Resources Department, University of Campinas-UNICAMP, Av. Albert Einstein, 951, Cidade Universitaria-Barao Geraldo-Campinas, S.P., 13083-852 (Brazil)

2010-08-15

It is known that the presence of trapped air within water distribution pipes can lead to irregular operation or even damage to the distribution systems and their components. The presence of trapped air may occur while the pipes are being filled with water, or while the pumping systems are in operation. The formation of large air pockets can produce the water hammer phenomenon, the instability and the loss of pressure in the water distribution networks. As a result, it can overload the pumps, increase the consumption of electricity, and damage the pumping system. In order to avoid its formation, all of the trapped air should be removed through 'air trap valves'. In Brazil, manufacturers frequently have unreliable sizing charts, which cause malfunctioning of the 'air trap valves'. The result of these malfunctions causes accidents of substantial damage. The construction of a test facility will provide a foundation of technical information that will be used to help make decisions when designing a system of pipelines where 'air trap valves' are used. To achieve this, all of the valve characteristics (geometric, mechanic, hydraulic and dynamic) should be determined. This paper aims to describe and analyze the experimental apparatus and test procedure to be used to test 'air trap valves'. The experimental apparatus and test facility will be located at the University of Campinas, Brazil at the College of Civil Engineering, Architecture, and Urbanism in the Hydraulics and Fluid Mechanics laboratory. The experimental apparatus will be comprised of various components (pumps, steel pipes, butterfly valves to control the discharge, flow meter and reservoirs) and instrumentation (pressure transducers, anemometer and proximity sensor). It should be emphasized that all theoretical and experimental procedures should be defined while taking into consideration flow parameters and fluid properties that influence the tests.

Nuclear Test-Experimental Science: Annual report, fiscal year 1988

Energy Technology Data Exchange (ETDEWEB)

Struble, G.L.; Donohue, M.L.; Bucciarelli, G.; Hymer, J.D.; Kirvel, R.D.; Middleton, C.; Prono, J.; Reid, S.; Strack, B. (eds.)

1988-01-01

Fiscal year 1988 has been a significant, rewarding, and exciting period for Lawrence Livermore National Laboratory's nuclear testing program. It was significant in that the Laboratory's new director chose to focus strongly on the program's activities and to commit to a revitalized emphasis on testing and the experimental science that underlies it. It was rewarding in that revolutionary new measurement techniques were fielded on recent important and highly complicated underground nuclear tests with truly incredible results. And it was exciting in that the sophisticated and fundamental problems of weapons science that are now being addressed experimentally are yielding new challenges and understanding in ways that stimulate and reward the brightest and best of scientists. During FY88 the program was reorganized to emphasize our commitment to experimental science. The name of the program was changed to reflect this commitment, becoming the Nuclear Test-Experimental Science (NTES) Program.

Secondary Waste Cast Stone Waste Form Qualification Testing Plan

Energy Technology Data Exchange (ETDEWEB)

Westsik, Joseph H.; Serne, R. Jeffrey

2012-09-26

The Hanford Tank Waste Treatment and Immobilization Plant (WTP) is being constructed to treat the 56 million gallons of radioactive waste stored in 177 underground tanks at the Hanford Site. The WTP includes a pretreatment facility to separate the wastes into high-level waste (HLW) and low-activity waste (LAW) fractions for vitrification and disposal. The LAW will be converted to glass for final disposal at the Integrated Disposal Facility (IDF). Cast Stone – a cementitious waste form, has been selected for solidification of this secondary waste stream after treatment in the ETF. The secondary-waste Cast Stone waste form must be acceptable for disposal in the IDF. This secondary waste Cast Stone waste form qualification testing plan outlines the testing of the waste form and immobilization process to demonstrate that the Cast Stone waste form can comply with the disposal requirements. Specifications for the secondary-waste Cast Stone waste form have not been established. For this testing plan, Cast Stone specifications are derived from specifications for the immobilized LAW glass in the WTP contract, the waste acceptance criteria for the IDF, and the waste acceptance criteria in the IDF Permit issued by the State of Washington. This testing plan outlines the testing needed to demonstrate that the waste form can comply with these waste form specifications and acceptance criteria. The testing program must also demonstrate that the immobilization process can be controlled to consistently provide an acceptable waste form product. This testing plan also outlines the testing needed to provide the technical basis for understanding the long-term performance of the waste form in the disposal environment. These waste form performance data are needed to support performance assessment analyses of the long-term environmental impact of the secondary-waste Cast Stone waste form in the IDF

Single Event Effects (SEE) Testing: Practical Approach to Test Plans

Science.gov (United States)

LaBel, Kenneth A.; Pellish, Jonathan Allen; Berg, Melanie D.

2014-01-01

While standards and guidelines for performing SEE testing have existed for several decades, guidance for developing SEE test plans has not been as easy to find. In this presentation, the variety of areas that need to be considered ranging from resource issues (funds, personnel, schedule) to extremely technical challenges (particle interaction and circuit application), shall be discussed. Note: we consider the approach outlined here as a "living" document: Mission-specific constraints and new technology related issues always need to be taken into account.

Permutation tests for goodness-of-fit testing of mathematical models to experimental data.

Science.gov (United States)

Fişek, M Hamit; Barlas, Zeynep

2013-03-01

This paper presents statistical procedures for improving the goodness-of-fit testing of theoretical models to data obtained from laboratory experiments. We use an experimental study in the expectation states research tradition which has been carried out in the "standardized experimental situation" associated with the program to illustrate the application of our procedures. We briefly review the expectation states research program and the fundamentals of resampling statistics as we develop our procedures in the resampling context. The first procedure we develop is a modification of the chi-square test which has been the primary statistical tool for assessing goodness of fit in the EST research program, but has problems associated with its use. We discuss these problems and suggest a procedure to overcome them. The second procedure we present, the "Average Absolute Deviation" test, is a new test and is proposed as an alternative to the chi square test, as being simpler and more informative. The third and fourth procedures are permutation versions of Jonckheere's test for ordered alternatives, and Kendall's tau(b), a rank order correlation coefficient. The fifth procedure is a new rank order goodness-of-fit test, which we call the "Deviation from Ideal Ranking" index, which we believe may be more useful than other rank order tests for assessing goodness-of-fit of models to experimental data. The application of these procedures to the sample data is illustrated in detail. We then present another laboratory study from an experimental paradigm different from the expectation states paradigm - the "network exchange" paradigm, and describe how our procedures may be applied to this data set. Copyright © 2012 Elsevier Inc. All rights reserved.

Test plan guidance for transuranic-contaminated arid landfill remedial technology development

International Nuclear Information System (INIS)

Evans, J.; Shaw, P.

1995-05-01

This document provides guidance for preparing plans to test or demonstrate buried waste assessment or remediation technologies supported by the U.S. Department of Energy's Landfill Stabilization Focus Area, Transuranic-Contaminated Arid Landfill Product Line. This document also provides guidance for development of data quality objectives, along with the necessary data to meet the project objectives. The purpose is to ensure that useful data of known quality are collected to support conclusions associated with the designated demonstration or test. A properly prepared test plan will integrate specific and appropriate objectives with needed measurements to ensure data will reflect the Department of Energy Office of Technology Development's mission, be consistent with Landfill Stabilization Focus Area test goals, and be useful for the Department of Energy Environmental Restoration and Waste Management programs and other potential partners (e.g., commercial concerns). The test plan becomes the planning and working document for the demonstration or test to be conducted ensuring procedures are followed that will allow data of sufficient quality to be collected for comparison and evaluation

Nuclear test-experimental science annual report, Fiscal year 1990

International Nuclear Information System (INIS)

Struble, G.L.; Middleton, C.; Anderson, S.E.; Cherniak, J.; Donohue, M.L.; Francke, A.; Hedman, I.; Kirvel, R.D.

1991-01-01

Fiscal year 1990 was another year of outstanding accomplishments for the Nuclear Test-Experimental Science (NTES) Program at Lawrence Livermore National Laboratory (LLNL). We continued to make progress to enhance the experimental science in the Weapons Program and to improve the operational efficiency and productivity of the Nuclear Test Program

Treatability Test Plan for an In Situ Biostimulation Reducing Barrier

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J.; Vermeul, Vince R.; Long, Philip E.; Brockman, Fred J.; Oostrom, Mart; Hubbard, Susan; Borden, Robert C.; Fruchter, Jonathan S.

2007-07-21

This treatability test plan supports a new, integrated strategy to accelerate cleanup of chromium in the Hanford 100 Areas. This plan includes performing a field-scale treatability test for bioreduction of chromate, nitrate, and dissolved oxygen. In addition to remediating a portion of the plume and demonstrating reduction of electron acceptors in the plume, the data from this test will be valuable for designing a full-scale bioremediation system to apply at this and other chromium plumes at Hanford.

Test plan for Fauske and Associates to perform tube propagation experiments with simulated Hanford tank wastes

International Nuclear Information System (INIS)

Carlson, C.D.; Babad, H.

1996-05-01

This test plan, prepared at Pacific Northwest National Laboratory for Westinghouse Hanford Company, provides guidance for performing tube propagation experiments on simulated Hanford tank wastes and on actual tank waste samples. Simulant compositions are defined and an experimental logic tree is provided for Fauske and Associates (FAI) to perform the experiments. From this guidance, methods and equipment for small-scale tube propagation experiments to be performed at the Hanford Site on actual tank samples will be developed. Propagation behavior of wastes will directly support the safety analysis (SARR) for the organic tanks. Tube propagation may be the definitive tool for determining the relative reactivity of the wastes contained in the Hanford tanks. FAI have performed tube propagation studies previously on simple two- and three-component surrogate mixtures. The simulant defined in this test plan more closely represents actual tank composition. Data will be used to support preparation of criteria for determining the relative safety of the organic bearing wastes

Field test plan: Buried waste technologies, Fiscal Year 1995

International Nuclear Information System (INIS)

Heard, R.E.; Hyde, R.A.; Engleman, V.S.; Evans, J.D.; Jackson, T.W.

1995-06-01

The US Department of Energy, Office of Technology Development, supports the applied research, development, demonstration, testing, and evaluation of a suite of advanced technologies that, when integrated with commercially available baseline technologies, form a comprehensive remediation system for the effective and efficient remediation of buried waste. The Fiscal Year 1995 effort is to deploy and test multiple technologies from four functional areas of buried waste remediation: site characterization, waste characterization, retrieval, and treatment. This document is the basic operational planning document for the deployment and testing of the technologies that support the field testing in Fiscal Year 1995. Discussed in this document are the scope of the tests; purpose and objective of the tests; organization and responsibilities; contingency plans; sequence of activities; sampling and data collection; document control; analytical methods; data reduction, validation, and verification; quality assurance; equipment and instruments; facilities and utilities; health and safety; residuals management; and regulatory management

Overview of planning process at FFTF [Fast Flux Test Facility

International Nuclear Information System (INIS)

Gadeken, A.D.

1986-03-01

The planning process at the Fast Flux Test Facility (FFTF) is controlled through a hierarchy of documents ranging from a ten-year strategic plan to a weekly schedule. Within the hierarchy are a Near-Term (three-year) Operating Plan, a Cycle (six-month) Plan, and an Outage/Operating Phase Schedule. Coordination of the planning process is accomplished by a dedicated preparation team that also provides an overview of the formal planning timetable which identifies key action items required to be completed before an outage/operating phase can begin

Radiation planning in small complex lesions and experimental verification

International Nuclear Information System (INIS)

Jess-Hempen, A.; Wowra, B.; Mack, A.; Kreiner, H.J.; Heck, B.

2003-01-01

The Gamma Knife is used as a sterotactic tool for the conformal treatment of very small, complex-shape cranial lesions. The combination of planning software and treatment equipment enables a highly-precise conformal dose distribution and positioning. The purpose of the present study was to experimentally verify the precision actually achievable in case of extremely irregular, small target volumes. For this purpose, a complete treatment procedure was performed using a standard head phantom complemented with a specially developed insert that simulates an L-shaped lesion. The spatial precision of the irradiation was recorded by means of high-resolution film dosimetry using GafChromic TM films. The analysis of the films showed for the film in the center plane an excellent conformity of the 75% isodose line used to circumscribe the lesion. A very good agreement between planning and measurement resulted also for isodose lines residing outside of the target volume. (orig.) [de

Experimental tests of relativistic gravity

International Nuclear Information System (INIS)

Damour, Thibault

2000-01-01

The confrontation between Einstein's gravitation theory and experimental results, notably binary pulsar data, is summarized and its significance discussed. Experiment and theory agree at the 10 -3 level or better. All the basic structures of Einstein's theory (coupling of gravity matter; propagation and self-interaction of the gravitational field, including in strong field conditions) have been verified. However, the theoretical possibility that scalar couplings be naturally driven toward zero by the cosmological expansion suggests that the present agreement between Einstein's theory and experiment might be compatible with the existence of a long-range scalar contribution to gravity (such as the dilation field, or a moduli field, of string theory). This provides a new theoretical paradigm, and new motivations for improving the experimental tests of gravity

Pilot-scale treatability test plan for the 200-UP-1 groundwater Operable Unit

International Nuclear Information System (INIS)

Wittreich, C.D.

1994-05-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-UP-1 Operable Unit. This treatability test plan has been prepared in response to an agreement between the US Department of Energy, the US Environmental Protection Agency, and the Washington State Department of Ecology, as documented in Hanford Federal Facility Agreement and Consent Order (Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994). The agreement also requires that, following completion of the activities described in this test plan, a 200-UP-1 Operable Unit interim remedial measure (IRM) proposed plan be developed for use in preparing an interim action record of decision (ROD). The IRM Proposed Plan will be supported by the results of the testing described in this treatability test plan, as well as by other 200-UP-1 Operable Unit activities (e.g., limited field investigation, development of a qualitative risk assessment). Once issued, the interim action ROD will specify the interim action for groundwater contamination at the 200-UP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-UP-1 Operable Unit. Primary contaminants of concern are uranium and technetium-99; the secondary contaminant of concern is nitrate. The pilot-scale treatability testing presented in this test plan has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants in groundwater withdrawn from the contaminant plume

Treatability Test Plan for an In Situ Biostimulation Reducing Barrier

Energy Technology Data Exchange (ETDEWEB)

Truex, Michael J.; Vermeul, Vince R.; Long, Philip E.; Brockman, Fred J.; Oostrom, Mart; Hubbard, Susan; Borden, Robert C.; Fruchter, Jonathan S.

2007-10-26

This treatability test plan supports a new, integrated strategy to accelerate cleanup of chromium in the 100 Areas at the Hanford Site. This plan includes performing a field-scale treatability test for bioreduction of chromate, nitrate, and dissolved oxygen. In addition to remediating a portion of the plume and demonstrating reduction of electron acceptors in the plume, the data from this test will be valuable for designing a full-scale bioremediation system to apply at this and other chromium plumes at the Hanford Site.

Test plan for Series 2 spent fuel cladding containment credit tests

International Nuclear Information System (INIS)

Wilson, C.N.

1984-10-01

This test plan describes a second series of tests to be conducted by Westinghouse Hanford Company (WHC) to evaluate the effectiveness of breached cladding as a barrier to radionuclide release in the NNWSI-proposed geologic repository. These tests will be conducted at the Hanford Engineering Development Laboratory (HEDL). A first series of tests, initiated at HEDL during FY 1983, demonstrated specimen preparation and feasibility of the testing concept. The second series tests will be similar to the Series 1 tests with the following exceptions: NNWSI reference groundwater obtained from well J-13 will be used as the leachant instead of deionized water; fuel from a second source will be used; and certain refinements will be made in specimen preparation, sampling, and analytical procedures. 12 references, 5 figures, 5 tables

Treatability test plan for the 200-ZP-1 operable unit

International Nuclear Information System (INIS)

1994-07-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-ZP-1 Operable Unit. The approach discussed in this treatability test plan is to conduct a pilot-scale pump and treat test for the contaminant plume associated with the 200-ZP-1 Operable Unit. The primary contaminants of concern are carbon tetrachloride, chloroform, and trichloroethylene (TCE). The pilot-scale treatability testing has as its primary purpose to assess the performance of aboveground treatment systems with respect to the ability to remove the primary contaminants present in groundwater withdrawn from the contaminant plume. The overall scope of this test plan includes: description of the pump and treat system to be tested, as well as the test performance objectives and data quality objectives (DQOs) that will be used to evaluate the effectiveness of the pilot-scale treatment system; discussion of the treatment technology to be tested and supporting development activities, including process flow and conceptual design descriptions and equipment, fabrication, utility, and system startup needs; description of pilot-scale treatment system performance, operating procedures, and operational controls, as well as anticipated monitoring activities, analytes, parameters, analytical procedures, and quality assurance protocols; summaries of other related treatability testing elements, including personnel and environmental health and safety controls, process and secondary waste management and disposition, schedule, and program organization

Integrated test plan for directional boring

International Nuclear Information System (INIS)

Volk, B.W.

1993-01-01

This integrated test plan describes the field testing of the DITCH WITCH Directional Boring System. DITCH WITCH is a registered trademark of The Charles Machine Works, Inc., Perry, Oklahoma. The test is being conducted as a coordinated effort between Charles Machine Works (CMW), Sandia National Laboratories (SNL), and the Westinghouse Hanford Company (WHC). Funding for the WHC portion of the project is through the Volatile Organic Compound-Arid Integrated Demonstration (VOC-Arid ID). The purpose of the test is to evaluate the performance of the directional boring system for possible future use on environmental restoration projects at Hanford and other Department of Energy (DOE) sites. The test will be conducted near the 200 Areas Fire Station located between the 200 East and 200 West Area of the Hanford Site. The directional boring system will be used to drill and complete (with fiberglass casing) two horizontal boreholes. A third borehole will be drilled to test sampling equipment but will not be completed with casing

Standard Ship Test and Inspection Plan, Procedures and Database

National Research Council Canada - National Science Library

1999-01-01

... construction schedules and increased cost is the area of test and inspection. This project investigates existing rules and regulations for testing and inspection of commercial ships and identifies differences and similarities within the requirements. The results include comparison matrices, a standard test plan, a set of standard test procedures, and a sample test database developed for a typical commercial ship.

Verifying seismic design of nuclear reactors by testing. Volume 1: test plan

Energy Technology Data Exchange (ETDEWEB)

1979-07-20

This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program.

Verifying seismic design of nuclear reactors by testing. Volume 1: test plan

International Nuclear Information System (INIS)

1979-01-01

This document sets forth recommendations for a verification program to test the ability of operational nuclear power plants to achieve safe shutdown immediately following a safe-shutdown earthquake. The purpose of the study is to develop a program plan to provide assurance by physical demonstration that nuclear power plants are earthquake resistant and to allow nuclear power plant operators to (1) decide whether tests should be conducted on their facilities, (2) specify the tests that should be performed, and (3) estimate the cost of the effort to complete the recommended test program

Test plan: Brayton Isotope Power System Ground Demonstration System (BIPS-GDS)

International Nuclear Information System (INIS)

1976-01-01

The purpose of this test plan is to provide an overall outline of all testing to be accomplished on the GDS. Included in this test plan are administrative requirements, instrumentation accuracies, instrumentation, equipment definitions, system test setup, and facility installation. The test program will enable collection of sufficient data to establish material, component, and system design integrity. The data will also be used to establish and evaluate component and system performance and reliability characteristics, verification of proper system component integration prior to initiation of Phase II, and flight system (FS) development

Aquifer test plan for the 100-HR-3 Operable Unit

International Nuclear Information System (INIS)

Swanson, L.C.; Hartman, M.J.

1994-01-01

This test plan directs hydrologic testing activities planned at three existing Comprehensive Environmental Response, Compensation, and Liability Act of 1980 (CERCLA) wells in the 100-HR-3 Operable Unit of the Hanford Site. Three additional wells will be installed near these existing wells and used as additional testing arid observation points during the field activities. Figure 1 shows the locations of the three test sites. A primary objective of the testing program is to provide more detailed hydraulic characterization information for the unconfined aquifer and targeted test sites than provided by the initial reconnaissance-level slug testing of Vukelich. A second objective is to evaluate the applicability of slug interference and dipole flow tests for detailed hydraulic characterization in an unconfined aquifer. This aquifer testing program will also be useful for substantiating hydraulic conductivities reported from previous slug tests and evaluating the effects of filter pack volume/configuration on slug test data. Vukelich recommended additional testing to address the latter two issues

Project W-314 specific test and evaluation plan 241-AN-B valve pit

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AN-B Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP)

In situ treatability test plan

International Nuclear Information System (INIS)

1996-08-01

This document describes the plans for the in situ treatment zone (ISTZ) treatability test for groundwater contaminated with strontium-90. The treatability test is to be conducted at the Hanford Site in Richland, Washington, in a portion of the 100-N Area adjacent to the Columbia River referred to as N-Springs. The purpose of the treatability test is to evaluate the effectiveness of an innovative technology to prevent the discharge of strontium-90 contaminated groundwater into the Columbia River. The ISTZ is a passive technology that consists of placing a treatment agent in the path of the groundwater. The treatment agent must restrict target radioactive contaminants and provide time for the contaminant to decay to acceptable levels. The permeability of the treatment zone must be greater than or equal to that of the surrounding sediments to ensure that the contaminated groundwater flows through the treatment zone agent and not around the agent

General Vehicle Test Plan (GVTP) for Urban Rail Transit Cars

Science.gov (United States)

1977-09-01

The General Vehicle Test Plan provides a system for general vehicle testing and for documenting and utilizing data and information in the testing of urban rail transit cars. Test procedures are defined for nine categories: (1) Performance; (2) Power ...

Phase Startup Initiative Phases 3 and 4 Test Plan and Test Specification ( OCRWM)

Energy Technology Data Exchange (ETDEWEB)

PAJUNEN, A.L.; LANGEVIN, M.J.

2000-08-07

Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: Define the Phase 3 and 4 test scope for the FRS and IWTS; Provide detailed test requirements that can be used to write the specific test procedures; Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and Define specific test objectives and acceptance criteria.

Phase Startup Initiative Phases 3 and 4 Test Plan and Test Specification (OCRWM)

International Nuclear Information System (INIS)

PAJUNEN, A.L.; LANGEVIN, M.J.

2000-01-01

Construction for the Spent Nuclear Fuel (SNF) Project facilities is continuing per the Level III Baseline Schedule, and installation of the Fuel Retrieval System (FRS) and Integrated Water Treatment System (IWTS) in K West Basin is now complete. In order to accelerate the project, a phased start up strategy to initiate testing of the FRS and IWTS early in the overall project schedule was proposed (Williams 1999). Wilkinson (1999) expands the definition of the original proposal into four functional testing phases of the Phased Startup Initiative (PSI). Phases 1 and 2 are based on performing functional tests using dummy fuel. This test plan provides overall guidance for Phase 3 and 4 tests, which are performed using actual irradiated N fuel assemblies. The overall objective of the Phase 3 and 4 testing is to verify how the FRS and IWTS respond while processing actual fuel. Conducting these tests early in the project schedule will allow identification and resolution of equipment and process problems before they become activities on the start-up critical path. The specific objectives of this test plan are to: Define the Phase 3 and 4 test scope for the FRS and IWTS; Provide detailed test requirements that can be used to write the specific test procedures; Define data required and measurements to be taken. Where existing methods to obtain these do not exist, enough detail will be provided to define required additional equipment; and Define specific test objectives and acceptance criteria

Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

Energy Technology Data Exchange (ETDEWEB)

1981-12-01

This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs.

Integrated operations plan for the MFTF-B Mirror Fusion Test Facility. Volume II. Integrated operations plan

International Nuclear Information System (INIS)

1981-12-01

This document defines an integrated plan for the operation of the Lawrence Livermore National Laboratory (LLNL) Mirror Fusion Test Facility (MFTF-B). The plan fulfills and further delineates LLNL policies and provides for accomplishing the functions required by the program. This plan specifies the management, operations, maintenance, and engineering support responsibilities. It covers phasing into sustained operations as well as the sustained operations themselves. Administrative and Plant Engineering support, which are now being performed satisfactorily, are not part of this plan unless there are unique needs

GRIST-2 preliminary test plan and requirements for fuel fabrication and preirradiation

International Nuclear Information System (INIS)

Tang, I.M.; Harmon, D.P.; Torri, A.

1978-12-01

The preliminary version of the GRIST-2 test plan has been developed for the planned initial 5 years (1984 to 1989) of TREAT-Upgrade in-pile tests. These tests will be employed to study the phenomenology and integral behavior of GCFR core disruptive accidents (CDAs) and to support the Final Safety Analysis Report (FSAR) CDA analyses for the demonstration plant licensing. The preliminary test plan is outlined. Test Phases I and II are for the fresh fuel (preconditioned or not) CDA behavior at the beginning-of-life (BOL) reactor state. Phase III is for the reactor state that contains irradiated fuel with a saturated content of helium and fission gas. Phase IV is for larger bundle tests and scaling effects

Reliability Analysis and Test Planning using CAPO-Test for Existing Structures

DEFF Research Database (Denmark)

Sørensen, John Dalsgaard; Engelund, S.; Faber, Michael Havbro

2000-01-01

Evaluation of the reliability of existing concrete structures often requires that the compressive strength of the concrete is estimated on the basis of tests performed with concrete samples from the structure considered. In this paper the CAPO-test method is considered. The different sources...... of uncertainty related to this method are described. It is shown how the uncertainty in the transformation from the CAPO-test results to estimates of the concrete strength can be modeled. Further, the statistical uncertainty is modeled using Bayesian statistics. Finally, it is shown how reliability-based optimal...... planning of CAPO-tests can be performed taking into account the expected costs due to the CAPO-tests and possible repair or failure of the structure considered. An illustrative example is presented where the CAPO-test is compared with conventional concrete cylinder compression tests performed on cores...

Test plan: Hydraulic fracturing and hydrologic tests in Marker Beds 139 and 140

International Nuclear Information System (INIS)

Wawersik, W.R.; Beauheim, R.L.

1991-03-01

Combined hydraulic fracturing and hydrological measurements in this test plan are designed to evaluate the potential influence of fracture formation in anhydrite Marker Beds 139 and 140 on gas pressure in and gas flow from the disposal rooms in the Waste Isolation Pilot Plant with time. The tests have the further purpose of providing comparisons of permeabilities of anhydrite interbeds in an undisturbed (virgin) state and after fracture development and/or opening and dilation of preexisting partially healed fractures. Three sets of combined hydraulic fracturing and hydrological measurements are planned. A set of trial measurements is expected to last four to six weeks. The duration of each subsequent experiment is anticipated to be six to eight weeks

Reliability demonstration test planning: A three dimensional consideration

International Nuclear Information System (INIS)

Yadav, Om Prakash; Singh, Nanua; Goel, Parveen S.

2006-01-01

Increasing customer demand for reliability, fierce market competition on time-to-market and cost, and highly reliable products are making reliability testing more challenging task. This paper presents a systematic approach for identifying critical elements (subsystems and components) of the system and deciding the types of test to be performed to demonstrate reliability. It decomposes the system into three dimensions (i.e. physical, functional and time) and identifies critical elements in the design by allocating system level reliability to each candidate. The decomposition of system level reliability is achieved by using criticality index. The numerical value of criticality index for each candidate is derived based on the information available from failure mode and effects analysis (FMEA) document or warranty data from a prior system. It makes use of this information to develop reliability demonstration test plan for the identified (critical) failure mechanisms and physical elements. It also highlights the benefits of using prior information in order to locate critical spots in the design and in subsequent development of test plans. A case example is presented to demonstrate the proposed approach

Project W-314 Polyurea Special Protective Coating (SPC) Test Plan Chemical Compatibility and Physical Characteristics Testing

International Nuclear Information System (INIS)

MAUSER, R.W.

2001-01-01

This Test Plan outlines the testing to be done on the Special Protective Coating (SPC) Polyurea which includes: Tank Waste Compatibility, Decontamination Factor Testing, and Adhesion Strength Testing after a sample has been exposed to Radiation

Test plan/procedure for the SPM-1 shipping container system. Revision 0

International Nuclear Information System (INIS)

Flanagan, B.D.

1995-01-01

The 49 CFR 173.465 Type A packaging tests will verify that SPM-1 will provide adequate protection and pass as a Type A package. Test will determine that the handle of the Pig will not penetrate through the plywood spacer and rupture the shipping container. Test plan/procedure provides planning, pre-test, setup, testing, and post-testing guidelines and procedures for conducting the open-quotes Free Drop Testclose quotes procedure for the SPM-1 package

Test and Evaluation for Enhanced Security: A Quantitative Method to Incorporate Expert Knowledge into Test Planning Decisions.

Energy Technology Data Exchange (ETDEWEB)

Rizzo, Davinia [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Blackburn, Mark [Stevens Inst. of Technology, Hoboken, NJ (United States)

2017-03-01

Complex systems are comprised of technical, social, political and environmental factors as well as the programmatic factors of cost, schedule and risk. Testing these systems for enhanced security requires expert knowledge in many different fields. It is important to test these systems to ensure effectiveness, but testing is limited to due cost, schedule, safety, feasibility and a myriad of other reasons. Without an effective decision framework for Test and Evaluation (T&E) planning that can take into consideration technical as well as programmatic factors and leverage expert knowledge, security in complex systems may not be assessed effectively. Therefore, this paper covers the identification of the current T&E planning problem and an approach to include the full variety of factors and leverage expert knowledge in T&E planning through the use of Bayesian Networks (BN).

Industrial tests of rhodium self-powered detectors: the Golfech 2 experimentation

International Nuclear Information System (INIS)

Mourlevat, J.L.; Janvier, D.; Warren, H.D.

2000-01-01

In co-operation with Electricite de France (EDF), FRAMATOME has been testing two in-core strings which are equipped with rhodium self-powered detectors (SPDs) in the Golfech Unit 2 reactor (1300 MW, 4L plant) since August 1997. The rhodium SPDs and the strings which support them were designed and built by the US FRAMATOME subsidiary FRAMATOME-COGEMA-FUEL (FCF). The rhodium signals and some other plant parameters are acquired through the use of a specific device designed by the CEA (Commissariat a l'Energie Atomique) and are processed off-line by FRAMATOME. This demonstration test is planned to last until mid-2000. The following presentation is focused on the results obtained during the first demonstration cycle (from 08/97 to 12/98). The tests that have been conducted consist of checking the rhodium depletion and of comparing the rhodium signals to the movable probes. In order to compensate for the delay in the rhodium signals, a deconvolution algorithm has also been tested. Up to now, the results are very satisfactory and a future large scale industrial application is being discussed with the EDF. The main objective of the next experimentation phase is to test - under industrial conditions - a prototype of an on-line monitoring unit known as the Partial In-Core Monitoring System (PIMS). This system will include 16 rhodium in-core strings and will use an on-line 3-D core model. (authors)

Test plan, sludge retrieval, sludge packaging

International Nuclear Information System (INIS)

Feigenbutz, L.V.

1994-01-01

This document provides direction for the cold testing of tools, equipment and systems which will be installed and operated in K-East (KE) Basin in support of the sludge retrieval and packaging project. The technical uncertainties related to the effectiveness of sludge retrieval procedures and equipment require that cold testing be completed before installation in KE Basin to identify and resolve existing problems, and to optimize the efficiency of all equipment and systems used. This plan establishes the responsibilities, test requirements, and documentation requirements necessary to complete cold tests of: (1) equipment with no potential for plant use; (2) prototype equipment and systems which may be upgraded for use in K-Basin; and (3) plant equipment and systems requiring cold acceptance testing prior to plant use. Some equipment and systems may have been subject to a formal design review and safety assessment; the results of which will be included as supporting documents to the operational readiness review (ORR)

Pilot-scale treatability test plan for the 200-BP-5 operable unit

International Nuclear Information System (INIS)

1994-08-01

This document presents the treatability test plan for pilot-scale pump and treat testing at the 200-BP-5 Operable Unit. This treatability test plan has been prepared in response to an agreement between the U.S. Department of Energy (DOE), the U.S. Environmental Protection Agency (EPA), and the State of Washington Department of Ecology (Ecology), as documented in Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement, Ecology et al. 1989a) Change Control Form M-13-93-03 (Ecology et al. 1994) and a recent 200 NPL Agreement Change Control Form (Appendix A). The agreement also requires that, following completion of the activities described in this test plan, a 200-BP-5 Operable Unit Interim Remedial Measure (IRM) Proposed Plan be developed for use in preparing an Interim Action Record of Decision (ROD). The IRM Proposed Plan will be supported by the results of this treatability test plan, as well as by other 200-BP-5 Operable Unit activities (e.g., development of a qualitative risk assessment). Once issued, the Interim Action ROD will specify the interim action(s) for groundwater contamination at the 200-BP-5 Operable Unit. The treatability test approach is to conduct a pilot-scale pump and treat test for each of the two contaminant plumes associated with the 200-BP-5 Operable Unit. Primary contaminants of concern are 99 Tc and 60 Co for underwater affected by past discharges to the 216-BY Cribs, and 90 Sr, 239/240 Pu, and Cs for groundwater affected by past discharges to the 216-B-5 Reverse Well. The purpose of the pilot-scale treatability testing presented in this testplan is to provide the data basis for preparing an IRM Proposed Plan. To achieve this objective, treatability testing must: Assess the performance of groundwater pumping with respect to the ability to extract a significant amount of the primary contaminant mass present in the two contaminant plumes

Test phase plan for the Waste Isolation Pilot Plant

International Nuclear Information System (INIS)

1993-03-01

The US Department of Energy (DOE) has prepared this Test Phase Plan for the Waste Isolation Pilot Plant to satisfy the requirements of Public Law 102-579, the Waste Isolation Pilot Plant (WIPP) Land Withdrawal Act (LWA). The Act provides seven months after its enactment for the DOE to submit this Plan to the Environmental Protection Agency (EPA) for review. A potential geologic repository for transuranic wastes, including transuranic mixed wastes, generated in national-defense activities, the WIPP is being constructed in southeastern New Mexico. Because these wastes remain radioactive and chemically hazardous for a very long time, the WIPP must provide safe disposal for thousands of years. The DOE is developing the facility in phases. Surface facilities for receiving waste have been built and considerable underground excavations (2150 feet below the surface) that are appropriate for in-situ testing, have been completed. Additional excavations will be completed when they are required for waste disposal. The next step is to conduct a test phase. The purpose of the test phase is to develop pertinent information and assess whether the disposal of transuranic waste and transuranic mixed waste in the planned WIPP repository can be conducted in compliance with the environmental standards for disposal and with the Solid Waste Disposal Act (SWDA) (as amended by RCRA, 42 USC. 6901 et. seq.). The test phase includes laboratory experiments and underground tests using contact-handled transuranic waste. Waste-related tests at WIPP will be limited to contact-handled transuranic and simulated wastes since the LWA prohibits the transport to or emplacement of remote-handled transuranic waste at WIPP during the test phase

Experimental testing of constructivism and related theories.

Science.gov (United States)

Fidelman, U

1991-10-01

The purpose of this article is to show that experimental scientific methods can be applied to explain how the analytic mechanism of the left cerebral hemisphere and the synthetic mechanism of the right one create complex cognitive constructions like ontology and mathematics. Nominalism and ordinal mathematical concepts are related to the analytic left hemisphere while Platonism and cardinal mathematical concepts are related to the synthetic right one. Thus persons with a dominant left hemisphere tend to prefer nominalist ontology and have more aptitude for ordinal mathematics than for cardinal mathematics, while persons with a dominant right hemisphere tend to prefer platonist ontology and have more aptitude for cardinal mathematics than for ordinal mathematics. It is further explained how the Kantism temporal mode of perceiving experience can be related to the left hemisphere while the Kantian spatial mode of perceiving experience can be related to the right hemisphere. This relation can be tested experimentally, thus the Kantian source of constructivism, and through it constructivism itself, can be tested experimentally.

Standard review plan for the review and evaluation of emergency plans for research and test reactors. Technical report

International Nuclear Information System (INIS)

Bates, E.F.; Grimes, B.K.; Ramos, S.L.

1982-05-01

This document provides a Standard Review Plan for the guidance of the NRC staff to assure that complete and uniform reviews are made of research and test reactor emergency plans. The report is organized under ten planning standards which correspond to the guidance criteria in Draft II of ANSI/ANS 15.16 as endorsed by Revision 1 to Regulatory Guide 2.6. The applicability of the items under each planning standard is indicated by subdivisions of the steady state thermal power levels at which the reactors are licensed to operate. Standard emergency classes and example action levels for research and test reactors which should initiate these classes are given in an Appendix

Front-end Electronics for Unattended Measurement (FEUM). Prototype Test Plan

Energy Technology Data Exchange (ETDEWEB)

Conrad, Ryan C.; Morris, Scott J.; Smith, Leon E.; Keller, Daniel T.

2015-09-16

The IAEA has requested that PNNL perform an initial set of tests on front-end electronics for unattended measurement (FEUM) prototypes. The FEUM prototype test plan details the tests to be performed, the criteria for evaluation, and the procedures used to execute the tests.

Experimental testing of exchangeable cutting inserts cutting ability

OpenAIRE

Čep, Robert; Janásek, Adam; Čepová, Lenka; Petrů, Jana; Hlavatý, Ivo; Car, Zlatan; Hatala, Michal

2013-01-01

The article deals with experimental testing of the cutting ability of exchangeable cutting inserts. Eleven types of exchangeable cutting inserts from five different manufacturers were tested. The tested cutting inserts were of the same shape and were different especially in material and coating types. The main aim was both to select a suitable test for determination of the cutting ability of exchangeable cutting inserts and to design such testing procedure that could make it possible...

Application of mathematical experimental planning in the investigation of thermodynamic properties of three- component alloys

International Nuclear Information System (INIS)

Sokolovskaya, E.M.; Guzej, L.S.; Tikhankin, G.A.; Meshkov, L.L.

1977-01-01

Thermodynamic properties of solid solutions of niobium and tungsten in nickel have been investigated by the method of electromotive forces with the use of simplex-matrix experiment planning techniques. The planning matrix and the results of investigating the thermodynamic properties of alloys of the nickel-niobium-tungsten system at 1250 deg are presented. The application of experiment planning has made it possible to obtain sufficient information concerning the thermodynamics of solid solutions of niobium and tungsten in nickel from the experimental data for six ternary alloys only

Field Lysimeter Test Facility for protective barriers: Experimental plan

International Nuclear Information System (INIS)

Kirkham, R.R.; Gee, G.W.; Downs, J.L.

1987-12-01

This document was first written in October 1986 and has been used to guide the design of the Field Lysimeter Test Facility (FLTF) and to promote discussions between research and engineering staff regarding the selection of barrier treatments for inclusion in the FLTF. The construction of the lysimeter facility was completed June 28, 1987. This document describes the facility, the treatments placed in each lysimeter, types of measurements made in each lysimeter, and a brief discussion of project activities related to quality assurance, safety, and funding requirements. The treatment description and figures have been updated to reflect the lysimeter facility as constructed. 12 refs., 6 figs., 5 tabs

Development of a fault test experimental facility model using Matlab

Energy Technology Data Exchange (ETDEWEB)

Pereira, Iraci Martinez; Moraes, Davi Almeida, E-mail: martinez@ipen.br, E-mail: dmoraes@dk8.com.br [Instituto de Pesquisas Energeticas e Nucleares (IPEN/CNEN-SP), Sao Paulo, SP (Brazil)

2015-07-01

The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

Development of a fault test experimental facility model using Matlab

International Nuclear Information System (INIS)

Pereira, Iraci Martinez; Moraes, Davi Almeida

2015-01-01

The Fault Test Experimental Facility was developed to simulate a PWR nuclear power plant and is instrumented with temperature, level and pressure sensors. The Fault Test Experimental Facility can be operated to generate normal and fault data, and these failures can be added initially small, and their magnitude being increasing gradually. This work presents the Fault Test Experimental Facility model developed using the Matlab GUIDE (Graphical User Interface Development Environment) toolbox that consists of a set of functions designed to create interfaces in an easy and fast way. The system model is based on the mass and energy inventory balance equations. Physical as well as operational aspects are taken into consideration. The interface layout looks like a process flowchart and the user can set the input variables. Besides the normal operation conditions, there is the possibility to choose a faulty variable from a list. The program also allows the user to set the noise level for the input variables. Using the model, data were generated for different operational conditions, both under normal and fault conditions with different noise levels added to the input variables. Data generated by the model will be compared with Fault Test Experimental Facility data. The Fault Test Experimental Facility theoretical model results will be used for the development of a Monitoring and Fault Detection System. (author)

Quality assurance: Fundamental reproducibility tests for 3D treatment‐planning systems

Science.gov (United States)

Able, Charles M.; Thomas, Michael D.

2005-01-01

The use of image‐based 3D treatment planning has significantly increased the complexity of commercially available treatment‐planning systems (TPSs). Medical physicists have traditionally focused their efforts on understanding the calculation algorithm; this is no longer possible. A quality assurance (QA) program for our 3D treatment‐planning system (ADAC Pinnacle3) is presented. The program is consistent with the American Association of Physicists in Medicine Task Group 53 guidelines and balances the cost‐versus‐benefit equation confronted by the clinical physicist in a community cancer center environment. Fundamental reproducibility tests are presented as required for a community cancer center environment using conventional and 3D treatment planning. A series of nondosimetric tests, including digitizer accuracy, image acquisition and display, and hardcopy output, is presented. Dosimetric tests include verification of monitor units (MUs), standard isodoses, and clinical cases. The tests are outlined for the Pinnacle3 TPS but can be generalized to any TPS currently in use. The program tested accuracy and constancy through several hardware and software upgrades to our TPS. This paper gives valuable guidance and insight to other physicists attempting to approach TPS QA at fundamental and practical levels. PACS numbers: 87.53.Tf, 87.53.Xd PMID:16143788

Planning the research and development necessary for accelerator transmutation of waste, leading to integrated proof of performance testing

International Nuclear Information System (INIS)

Bennett, D.R.; Pasamehmetoglu, K.; Finck, P.; Pitcher, E.; Khalil, H.; Todosow, M.; Hill, R.; Van Tuyle, G.; Laidler, J.; Crawford, D.; Thomas, K.

2001-01-01

The Research and Development (R and D) Plan for the Accelerator Transmutation of Waste (ATW) Program has been developed for the Department of Energy, Office of Nuclear Energy (DOE/NE) to serve as a focus and progressional guide in developing critical transmutation technologies. It is intended that the Plan will serve as a logical reference considering all elements of an integrated accelerator-driven transmutation system, and will maximize the use of resources by identifying and prioritizing research, design, development and trade activities. The R and D Plan provides a structured framework for identifying and prioritizing activities leading to technically-justifiable integrated Proof of Performance testing within ten years and ultimate demonstration of Accelerator Transmutation of Waste (ATW). The Plan builds from the decision objectives specified for ATW, utilizes informational input from the ATW Roadmap and programmatic System Point Design efforts, and employs the knowledge and expertise provided by professionals familiar with ATW technologies. With the firm intent of understanding what, why and when information is needed, including critical interfaces, the Plan then develops a progressional strategy for developing ATW technologies with the use of a Technology Readiness Level (TRL) scale. The TRL approach is first used to develop a comprehensive, yet generic, listing of experimental, analytical and trade study activities critical to developing ATW technologies. Technology-specific and concept-specific aspects are then laid over the generic mapping to gage readiness levels. Prioritization criteria for reducing technical uncertainty, providing information to decision points, and levering off of international collaborations are then applied to focus analytical, experimental and trade activities. (author)

Improved Test Planning and Analysis Through the Use of Advanced Statistical Methods

Science.gov (United States)

Green, Lawrence L.; Maxwell, Katherine A.; Glass, David E.; Vaughn, Wallace L.; Barger, Weston; Cook, Mylan

2016-01-01

The goal of this work is, through computational simulations, to provide statistically-based evidence to convince the testing community that a distributed testing approach is superior to a clustered testing approach for most situations. For clustered testing, numerous, repeated test points are acquired at a limited number of test conditions. For distributed testing, only one or a few test points are requested at many different conditions. The statistical techniques of Analysis of Variance (ANOVA), Design of Experiments (DOE) and Response Surface Methods (RSM) are applied to enable distributed test planning, data analysis and test augmentation. The D-Optimal class of DOE is used to plan an optimally efficient single- and multi-factor test. The resulting simulated test data are analyzed via ANOVA and a parametric model is constructed using RSM. Finally, ANOVA can be used to plan a second round of testing to augment the existing data set with new data points. The use of these techniques is demonstrated through several illustrative examples. To date, many thousands of comparisons have been performed and the results strongly support the conclusion that the distributed testing approach outperforms the clustered testing approach.

100 area excavation treatability test plan

International Nuclear Information System (INIS)

1993-05-01

This test plan documents the requirements for a treatability study on field radionuclide analysis and dust control techniques. These systems will be used during remedial actions involving excavation. The data from this treatability study will be used to support the feasibility study (FS) process. Development and screening of remedial alternatives for the 100 Area, using existing data, have been completed and are documented in the 100 Area Feasibility Study, Phases 1 and 2 (DOE-RL 1992a). Based on the results of the FS, the Treatability Study Program Plan (DOE-RL 1992b) identifies and prioritizes treatability studies for the 100 Area. The data from the treatability study program support future focused FS, interim remedial measures (IRM) selection, operable unit final remedy selection, remedial design, and remedial actions. Excavation is one of the high-priority, near-term, treatability study needs identified in the program plan (DOE-RL 1992b). Excavation of contaminated soils and buried solid wastes is included in several of the alternatives identified in the 100 Area FS. Although a common activity, excavation has only been used occasionally at the Hanford Site for waste removal applications

76 FR 2930 - Market Test of Experimental Product: “Gift Cards”

Science.gov (United States)

2011-01-18

... POSTAL SERVICE Market Test of Experimental Product: ``Gift Cards'' AGENCY: Postal Service \\TM\\. ACTION: Notice. SUMMARY: The Postal Service gives notice of a market test of an experimental product in... notice pursuant to 39 U.S.C. 3641(c)(1) that it will begin a market test of its ``Gift Cards...

Hanford Site physical separations CERCLA treatability test plan

International Nuclear Information System (INIS)

1992-03-01

This test plan describes specifications, responsibilities, and general procedures to be followed to conduct a physical separations soil treatability test in the North Process Pond of the 300-FF-1 Operable Unit at the Hanford Site, Washington. The objective of this test is to evaluate the use of physical separation systems as a means of concentrating chemical and radioactive contaminants into fine soil fractions and thereby minimizing waste volumes. If successful the technology could be applied to clean up millions of cubic meters of contaminated soils in waste sites at Hanford and other sites. It is not the intent of this test to remove contaminated materials from the fine soils. Physical separation is a simple and comparatively low cost technology to potentially achieve a significant reduction in the volume of contaminated soils. Organic contaminants are expected to be insignificant for the 300-FF-I Operable Unit test, and further removal of metals and radioactive contaminants from the fine fraction of soils will require secondary treatment such as chemical extraction, electromagnetic separation, or other technologies. Additional investigations/testing are recommended to assess the economic and technical feasibility of applying secondary treatment technologies, but are not within the scope of this test. This plan provides guidance and specifications for the treatability test to be conducted as a service contract. More detailed instructions and procedures will be provided as part of the vendors (sellers) proposal. The procedures will be approved by Westinghouse Hanford Company (Westinghouse Hanford) and finalized by the seller prior to initiating the test

EPRI/DOE High Burnup Fuel Sister Pin Test Plan Simplification and Visualization

Energy Technology Data Exchange (ETDEWEB)

Saltzstein, Sylvia J. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Sorenson, Ken B. [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States); Hanson, Brady [Pacific Northwest National Lab. (PNNL), Richland, WA (United States); Billone, Mike [Argonne National Lab. (ANL), Argonne, IL (United States); Scaglione, John [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Montgomery, Rose [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States); Bevard, Bruce [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)

2017-07-01

The EPRI/DOE High Burnup Confirmatory Data Project (herein called the "Demo") is a multi-year, multi-entity confirmation demonstration test with the purpose of providing quantitative and qualitative data to show how high-burnup fuel ages in dry storage over a ten-year period. The Demo involves obtaining 32 assemblies of high-burnup PWR fuel of four common cladding alloys from the North Anna Nuclear Power Plant, drying them according to standard plant procedures, and then storing them in an NRC-licensed TN-3 2B cask on the North Anna dry storage pad for ten years. After the ten-year storage time, the cask will be opened and the rods will be examined for signs of aging. Twenty-five rods from assemblies of similar claddings, in-reactor placement, and burnup histories (herein called "sister rods") have been shipped from the North Anna Nuclear Power Plant and are currently being nondestructively tested at Oak Ridge National Laboratory. After the non-destructive testing has been completed for each of the twenty-five rods, destructive analysis will be performed at ORNL, PNNL, and ANL to obtain mechanical data. Opinions gathered from the expert interviews, ORNL and PNNL Sister Rod Test Plans, and numerous meetings has resulted in the Simplified Test Plan described in this document. Some of the opinions and discussions leading to the simplified test plan are included here. Detailed descriptions and background are in the ORNL and PNNL plans in the appendices . After the testing described in this simplified test plan h as been completed , the community will review all the collected data and determine if additional testing is needed.

Test plan for FY-94 digface characterization field experiments

International Nuclear Information System (INIS)

Josten, N.E.; Roybal, L.G.

1994-08-01

The digface characterization concept has been under development at the Idaho National Engineering Laboratory (INEL) since fiscal year (FY) 1992 through the support of the Buried Waste Integrated Demonstration Program. A digface characterization system conducts continuous subsurface characterization simultaneously with retrieval of hazardous and radioactive waste from buried waste sites. The system deploys multiple sensors at the retrieval operation digface and collects data that provide a basis for detecting, locating, and classifying buried materials and hazardous conditions before they are disturbed by the retrieval equipment. This test plan describes ongoing efforts to test the digface characterization concept at the INEL's Cold Test Pit using a simplified prototype deployment apparatus and off-the-shelf sensors. FY-94 field experiments will explore problems in object detection and classification. Detection and classification of objects are fundamental to three of the four primary functions of digface characterization during overburden removal. This test plan establishes procedures for collecting and validating the digface characterization data sets. Analysis of these data will focus on testing and further developing analysis methods for object detection and classification during overburden removal

Fast Flux Test Facility project plan. Revision 2

Energy Technology Data Exchange (ETDEWEB)

Hulvey, R.K.

1995-11-01

The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition.

Fast Flux Test Facility project plan. Revision 2

International Nuclear Information System (INIS)

Hulvey, R.K.

1995-11-01

The Fast Flux Test Facility (FFTF) Transition Project Plan, Revision 2, provides changes to the major elements and project baseline for the deactivation activities necessary to transition the FFTF to a radiologically and industrially safe shutdown condition

Project W-314 specific test and evaluation plan for 241-AN-A valve pit

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AN-A Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP)

Effect of carboxymethylcellulose on the rheological and filtration properties of bentonite clay samples determined by experimental planning and statistical analysis

Directory of Open Access Journals (Sweden)

B. M. A. Brito

Full Text Available Abstract Over the past few years, considerable research has been conducted using the techniques of mixture delineation and statistical modeling. Through this methodology, applications in various technological fields have been found/optimized, especially in clay technology, leading to greater efficiency and reliability. This work studied the influence of carboxymethylcellulose on the rheological and filtration properties of bentonite dispersions to be applied in water-based drilling fluids using experimental planning and statistical analysis for clay mixtures. The dispersions were prepared according to Petrobras standard EP-1EP-00011-A, which deals with the testing of water-based drilling fluid viscosifiers for oil prospecting. The clay mixtures were transformed into sodic compounds, and carboxymethylcellulose additives of high and low molar mass were added, in order to improve their rheology and filtrate volume. Experimental planning and statistical analysis were used to verify the effect. The regression models were calculated for the relation between the compositions and the following rheological properties: apparent viscosity, plastic viscosity, and filtrate volume. The significance and validity of the models were confirmed. The results showed that the 3D response surfaces of the compositions with high molecular weight carboxymethylcellulose added were the ones that most contributed to the rise in apparent viscosity and plastic viscosity, and that those with low molecular weight were the ones that most helped in the reduction of the filtrate volume. Another important observation is that the experimental planning and statistical analysis can be used as an important auxiliary tool to optimize the rheological properties and filtrate volume of bentonite clay dispersions for use in drilling fluids when carboxymethylcellulose is added.

Plan for decommissioning the Tokamak Fusion Test Reactor

International Nuclear Information System (INIS)

Spampinato, P.T.; Walton, G.R.

1993-01-01

The Tokamak Fusion Test Reactor (TFTR) Project is in the planning phase of developing a decommissioning project. A Preliminary Decontamination and Decommissioning (D ampersand D) Plan has been developed which provides a framework for the baseline approach, and the cost and schedule estimates. TFTR will become activated and contaminated with tritium after completion of the deuterium-tritium (D-T) experiments. Hence some of the D ampersand D operations will require remote handling. It is expected that all of the waste generated will be low level radioactive waste (LLW). The objective of the D ampersand D Project is to make TFTR Test Cell available for use by a new fusion experiment. This paper discusses the D ampersand D objectives, the facility to be decommissioned, estimates of activation, the technical (baseline) approach, and the assumptions used to develop cost and schedule estimates

Prototype steam generator test at SCTI/ETEC. Acoustic program test plan

International Nuclear Information System (INIS)

Greene, D.A.; Thiele, A.; Claytor, T.N.

1981-10-01

This document is an integrated test plan covering programs at General Electric (ARSD), Rockwell International (RI) and Argonne National Laboratory (CT). It provides an overview of the acoustic leak detection test program which will be completed in conjunction with the prototype LMFBR steam generator at the Energy Technology Engineering Laboratory. The steam generator is installed in the Sodium Components Test Installation (SCTI). Two acoustic detection systems will be used during the test program, a low frequency system developed by GE-ARSD (GAAD system) and a high frequency system developed by RI-AI (HALD system). These systems will be used to acquire data on background noise during the thermal-hydraulic test program. Injection devices were installed during fabrication of the prototype steam generator to provide localized noise sources in the active region of the tube bundle. These injectors will be operated during the steam generator test program, and it will be shown that they are detected by the acoustic systems

Test Plan Addendum No. 1: Waste Isolation Pilot Plant bin-scale CH TRU waste tests

International Nuclear Information System (INIS)

Molecke, M.A.; Lappin, A.R.

1990-12-01

This document is the first major revision to the Test Plan: WIPP Bin-Scale CH TRU Waste Tests. Factors that make this revision necessary are described and justified in Section 1, and elaborated upon in Section 4. This addendum contains recommended estimates of, and details for: (1) The total separation of waste leaching/solubility tests from bin-scale gas tests, including preliminary details and quantities of leaching tests required for testing of Levels 1, 2, and 3 WIPP CH TRU wastes; (2) An initial description and quantification of bin-scale gas test Phase 0, added to provide a crucial tie to pretest waste characterization representatives and overall test statistical validation; (3) A revision to the number of test bins required for Phases 1 and 2 of the bin gas test program, and specification of the numbers of additional bin tests required for incorporating gas testing of Level 2 wastes into test Phase 3. Contingencies are stated for the total number of test bins required, both positive and negative, including the supporting assumptions, logic, and decision points. (4) Several other general test detail updates occurring since the Test Plan was approved and published in January, 1990. Possible impacts of recommended revisions included in this Addendum on WIPP site operations are called out and described. 56 refs., 12 tabs

Biomedical programs operations plans

Science.gov (United States)

Walbrecher, H. F.

1974-01-01

Operational guidelines for the space shuttle life sciences payloads are presented. An operational assessment of the medical experimental altitude test for Skylab, and Skylab life sciences documentation are discussed along with the operations posture and collection of space shuttle operational planning data.

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

International Nuclear Information System (INIS)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs

Project plan for the decontamination and decommissioning of the Argonne National Laboratory Experimental Boiling Water Reactor

Energy Technology Data Exchange (ETDEWEB)

Boing, L.E.

1989-12-01

In 1956, the Experimental Boiling Water Reactor (EBWR) Facility was first operated at Argonne National Laboratory (ANL) as a test reactor to demonstrate the feasibility of operating an integrated power plant using a direct cycle boiling water reactor as a heat source. In 1967, ANL permanently shut down the EBWR and placed it in dry lay-up. This project plan presents the schedule and organization for the decontamination and decommissioning of the EBWR Facility which will allow it to be reused by other ANL scientific research programs. The project total estimated cost is $14.3M and is projected to generate 22,000 cubic feet of low-level radioactive waste which will be disposed of at an approved DOE burial ground. 18 figs., 3 tabs.

Test, Control and Monitor System (TCMS) operations plan

Science.gov (United States)

Macfarlane, C. K.; Conroy, M. P.

1993-01-01

The purpose is to provide a clear understanding of the Test, Control and Monitor System (TCMS) operating environment and to describe the method of operations for TCMS. TCMS is a complex and sophisticated checkout system focused on support of the Space Station Freedom Program (SSFP) and related activities. An understanding of the TCMS operating environment is provided and operational responsibilities are defined. NASA and the Payload Ground Operations Contractor (PGOC) will use it as a guide to manage the operation of the TCMS computer systems and associated networks and workstations. All TCMS operational functions are examined. Other plans and detailed operating procedures relating to an individual operational function are referenced within this plan. This plan augments existing Technical Support Management Directives (TSMD's), Standard Practices, and other management documentation which will be followed where applicable.

Ice condenser testing facility and plans

International Nuclear Information System (INIS)

Kannberg, L.D.; Ross, B.A.; Eschbach, E.J.; Ligotke, M.W.

1987-01-01

A facility is being constructed to experimentally validate the ICEDF computer code. The code was developed to estimate the extent of fission product retention in the ice compartments of pressurized water reactor ice condenser containment systems during severe accidents. The design and construction of the facility is based on a test design that addresses the validation needs of the code for conditions typical of those expected to occur during severe pressurized water reactor accidents. Detailed facility design has followed completion of a test design (i.e., assembled test cases each involving a different set of aerosol and thermohydraulic flow conditions). The test design was developed with the aid of statistical test design software and was scrutinized for applicability with the aid of ICEDF simulations. The test facility will incorporate a small section of a prototypic ice condenser (e.g., a cross section comprising the equivalent of four 1-ft-diameter ice baskets to their full prototypic height of 48 ft). The development of the test design, the detailed facility design, and the construction progress are described in this paper

Test plan for the retrieval demonstration

International Nuclear Information System (INIS)

Valentich, D.J.

1993-05-01

This test plan describes a simulated buried waste retrieval demonstration that will be performed at the Caterpillar, Inc., Edwards Training Center located near Peoria, Illinois. The purpose of the demonstration is to determine the effectiveness of using readily available excavation equipment to retrieve, size, and handle various simulated waste forms that are similar in size, structure, and composition to those expected to be found in US Department of Energy contaminated waste pits and trenches. The objectives of this demonstration are to: meet and maintain daily production goals of 80 yd 3 /day; minimize spillage and dust generation through careful and deliberate operations; document and evaluate methods for manipulating, sizing, and/or working around large objects; and document and evaluate requirements for operator augmentation and remote operation for hot test pit excavation operations. Four conditions comprising the range of environments to be evaluated include excavation of random material from below grade; stacked boxes and barrels from below grade; random materials from at grade; and stacked boxes and barrels from at grade. Results of the retrieval demonstration will reduce unknowns in the body of knowledge about retrieval equipment and procedural options for removal of buried transuranic (TRU) waste at the Idaho National Engineering Laboratory. It is anticipated that DOE will factor this information into a remedial investigation/feasibility plan leading to a final record of decision for disposition of buried TRU waste

Out-pile test plan for lifetime extension of shutoff units in HANARO

Energy Technology Data Exchange (ETDEWEB)

Joe, Y. G.; Lee, J. H.; Jeong, Y. H.; Woo, S. I.; Ryu, J. S.; Kim, Y. G.; Park, Y. C.; Kim, H. G.; Woo, J. S. [KAERI, Taejon (Korea, Republic of)

2003-10-01

It is estimated that the number of drops of shutoff rods in HANARO will reach the endurance verified numbers before the end of the reactor life. To resolve this situation, we have a plan to prepare of a new spare unit by the performance verification test for the local product, and extend the lifetime of shutoff units installed in the reactor by performing an additional endurance test in the out-pile test facility using an existing spare unit. This paper describes the overall situations and test plan for the out-pile test to extend the lifetime extension of shutoff unit.

Group SkSP-R sampling plan for accelerated life tests

Indian Academy of Sciences (India)

Muhammad Aslam

2017-09-15

Sep 15, 2017 ... SkSP-R sampling; life test; Weibull distribution; producer's risk; ... designed a sampling plan under a time-truncated life test .... adjusted using an acceleration factor. ... where P is the probability of lot acceptance for a single.

Nevada test site radionuclide inventory and distribution: project operations plan

International Nuclear Information System (INIS)

Kordas, J.F.; Anspaugh, L.R.

1982-01-01

This document is the operational plan for conducting the Radionuclide Inventory and Distribution Program (RIDP) at the Nevada Test Site (NTS). The basic objective of this program is to inventory the significant radionuclides of NTS origin in NTS surface soil. The expected duration of the program is five years. This plan includes the program objectives, methods, organization, and schedules

Nuclear start-up, testing and core management of the Fast Test Reactor (FTR)

International Nuclear Information System (INIS)

Bennett, R.A.; Daughtry, J.W.; Harris, R.A.; Jones, D.H.; Nelson, J.V.; Rawlins, J.A.; Rothrock, R.B.; Sevenich, R.A.; Zimmerman, B.D.

1980-01-01

Plans for the nuclear start-up, low and high power physics testing, and core management of the Fast Test Reactor (FTR) are described. Owing to the arrangement of the fuel-handling system, which permits continuous instrument lead access to experiments during refuelling, it is most efficient to load the reactor in an asymmetric fashion, filling one-third core sectors at a time. The core neutron level will be monitored during this process using both in-core and ex-core detectors. A variety of physics tests are planned following the core loading. Because of the experimental purpose of the reactor, these tests will include a comprehensive characterization programme involving both active and passive neutron and gamma measurements. Following start-up tests, the FTR will be operated as a fast neutron irradiation facility, to test a wide variety of fast reactor core components and materials. Nuclear analyses will be made prior to each irradiation cycle to confirm that the planned arrangement of standard and experimental components satisfies all safety and operational constraints, and that all experiments are located so as to achieve their desired irradiation environment. (author)

Irradiated test fuel shipment plan for the LWR MOX fuel irradiation test project

International Nuclear Information System (INIS)

Shappert, L.B.; Dickerson, L.S.; Ludwig, S.B.

1998-01-01

This document outlines the responsibilities of DOE, DOE contractors, the commercial carrier, and other organizations participating in a shipping campaign of irradiated test specimen capsules containing mixed-oxide (MOX) fuel from the Idaho National Engineering and Environmental Laboratory (INEEL) to the Oak Ridge National Laboratory (ORNL). The shipments described here will be conducted according to applicable regulations of the US Department of Transportation (DOT), US Nuclear Regulatory Commission (NRC), and all applicable DOE Orders. This Irradiated Test Fuel Shipment Plan for the LWR MOX Fuel Irradiation Test Project addresses the shipments of a small number of irradiated test specimen capsules and has been reviewed and agreed to by INEEL and ORNL (as participants in the shipment campaign). Minor refinements to data entries in this plan, such as actual shipment dates, exact quantities and characteristics of materials to be shipped, and final approved shipment routing, will be communicated between the shipper, receiver, and carrier, as needed, using faxes, e-mail, official shipping papers, or other backup documents (e.g., shipment safety evaluations). Any major changes in responsibilities or data beyond refinements of dates and quantities of material will be prepared as additional revisions to this document and will undergo a full review and approval cycle

Generation of an activation map for decommissioning planning of the Berlin Experimental Reactor-II

Science.gov (United States)

Lapins, Janis; Guilliard, Nicole; Bernnat, Wolfgang

2017-09-01

The BER-II is an experimental facility with 10 MW that was operated since 1974. Its planned operation will end in 2019. To support the decommissioning planning, a map with the overall distribution of relevant radionuclides has to be created according to the state of the art. In this paper, a procedure to create these 3-d maps using a combination of MCNP and deterministic methods is presented. With this approach, an activation analysis is performed for the whole reactor geometry including the most remote parts of the concrete shielding.

Canister disposition plan for the DWPF Startup Test Program

International Nuclear Information System (INIS)

Harbour, J.R.; Payne, C.H.

1990-01-01

This report details the disposition of canisters and the canistered waste forms produced during the DWPF Startup Test Program. The six melter campaigns (DWPF Startup Tests FA-13, WP-14, WP-15, WP-16, WP-17, and FA-18) will produce 126 canistered waste forms. In addition, up to 20 additional canistered waste forms may be produced from glass poured during the transition between campaigns. In particular, this canister disposition plan (1) assigns (by alpha-numeric code) a specific canister to each location in the six campaign sequences, (2) describes the method of access for glass sampling on each canistered waste form, (3) describes the nature of the specific tests which will be carried out, (4) details which tests will be carried out on each canistered waste form, (5) provides the sequence of these tests for each canistered waste form, and (6) assigns a storage location for each canistered waste form. The tests are designed to provide evidence, as detailed in the Waste Form Compliance Plan (WCP 1 ), that the DWPF product will comply with the Waste Acceptance Product Specifications (WAPS 2 ). The WAPS must be met before the canistered waste form is accepted by DOE for ultimate disposal at the Federal Repository. The results of these tests will be included in the Waste Form Qualification Report (WQR)

Plan for metal barrier selection and testing for NNWSI

International Nuclear Information System (INIS)

Halsey, W.G.; McCright, R.D.

1987-12-01

The Department of Energy's Nevada Nuclear Waste Storage Investigations (NNWSI) Project is evaluating a site at Yucca Mountain in Nevada as a geological repository for the storage of high-level nuclear waste. The Nuclear Waste Management Projects (NWMP) at Lawrence Livermore National Laboratory (LLNL) has the responsibility for design, testing, and performance analysis of the NNWSI waste packages. One portion of this work is the selection and testing of the material for container construction. The anticipated container design is for this material to be a corrosion resistant metal called the metal barrier. This document is the publication version of the Scientific Investigation Plan (SIP) for the Metal Barrier Selection and Testing Task. The SIP serves as a formal planning document for the investigation and is used to assign quality assurance levels to the activities of the task. This document is an informal version for information distribution and has the sections on ''Schedule and Milestones'' and the ''Quality Assurance Level Assignment Sheets'' removed

Optimal integration and test plans for software releases of lithographic systems

NARCIS (Netherlands)

Boumen, R.; Jong, de I.S.M.; Mortel - Fronczak, van de J.M.; Rooda, J.E.

2007-01-01

This paper describes a method to determine the optimal integration and test plan for embedded systems software releases. The method consists of four steps: 1)describe the integration and test problem in an integration and test model which is introduced in this paper, 2) determine possible test

Hydrologic test plans for large-scale, multiple-well tests in support of site characterization at Hanford, Washington

International Nuclear Information System (INIS)

Rogers, P.M.; Stone, R.; Lu, A.H.

1985-01-01

The Basalt Waste Isolation Project is preparing plans for tests and has begun work on some tests that will provide the data necessary for the hydrogeologic characterization of a site located on a United States government reservation at Hanford, Washington. This site is being considered for the Nation's first geologic repository of high level nuclear waste. Hydrogeologic characterization of this site requires several lines of investigation which include: surface-based small-scale tests, testing performed at depth from an exploratory shaft, geochemistry investigations, regional studies, and site-specific investigations using large-scale, multiple-well hydraulic tests. The large-scale multiple-well tests are planned for several locations in and around the site. These tests are being designed to provide estimates of hydraulic parameter values of the geologic media, chemical properties of the groundwater, and hydrogeologic boundary conditions at a scale appropriate for evaluating repository performance with respect to potential radionuclide transport

Nuclear material control and accountancy planning and performance testing

International Nuclear Information System (INIS)

Mike Enhinger; Dennis Wilkey; Rod Martin; Ken Byers; Brian Smith

1999-01-01

An overview of performance testing as used at U.S. Department of Energy facilities is provided. Performance tests are performed on specific aspects of the regulations or site policy. The key issues in establishing a performance testing program are: identifying what needs to be tested; determining how to test; establishing criteria to evaluate test results. The program elements of performance testing program consist of: planning; coordination; conduct; evaluation. A performance test may be conducted of personnel or equipment. The DOE orders for nuclear material control and accountancy are divided into three functional areas: program administration, material accounting, and material control. Examples performance tests may be conducted on program administration, accounting, measurement and measurement control, inventory, and containment [ru

Heater test planning for the near surface test facility at the Hanford reservation

International Nuclear Information System (INIS)

DuBois, A.; Binnall, E.; Chan, T.; McEvoy, M.; Nelson, P.; Remer, J.

1979-03-01

The underground test facility NSTF being constructed at Gable Mountain, is the site for a group of experiments designed to evaluate the thermo-mechanical suitability of a deep basalt stratum as a permanent repository for nuclear waste. Thermo-mechanical modeling was performed to help design the instrumentation arrays for the three proposed heater tests (two full scale tests and one time scale test) and predict the thermal environment of the heaters and instruments. The modeling does not reflect recent RHO revisions to the in situ heater experiment plan. Heaters, instrumentation, and data acquisition system designs and recommendations were adapted from those used in Sweden

International Thermonuclear Experimental Reactor: Physics issues, capabilities and physics program plans

International Nuclear Information System (INIS)

Wesley, J.C.

1997-01-01

Present status and understanding of the principal plasma-performance determining physics issues that affect the physics design and operational capabilities of the International Thermonuclear Experimental Reactor (ITER) [ITER EDA Agreement and Protocol 2 (International Atomic Energy Agency, Vienna, 1994)] are presented. Emphasis is placed on the five major physics-basis issues emdash energy confinement, beta limit, density limit, impurity dilution and radiation loss, and the feasibility of obtaining partial-detached divertor operation emdash that directly affect projections of ITER fusion power and burn duration performance. A summary of these projections is presented and the effect of uncertainties in the physics-basis issues is examined. ITER capabilities for experimental flexibility and plasma-performance optimization are also described, and how these capabilities may enter into the ITER physics program plan is discussed. copyright 1997 American Institute of Physics

Project W-314 specific test and evaluation plan for 241-AY-02A pump pit upgrade

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

This Specific Test and Evaluation Plan (STEP) defines the test and evaluation activities encompassing the upgrade of the 241-AY-02A Pump Pit for the W-314 Project. The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AY-02A Pump Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP)

Project W-314 specific test and evaluation plan for 241-AY-01A pump pit upgrade

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

This Specific Test and Evaluation Plan (STEP) defines the test and evaluation activities encompassing the upgrade of the 241-AY-0IA Pump Pit for the W-314 Project. The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AY-01A Pump Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation Plan (TEP)

Career Planning Modules for the Officer Career Information and Planning System.

Science.gov (United States)

Phillips, Susan D.; And Others

This discussion of the modules in an experimental computer-aided system for officer career information and planning system (OCIPS) includes the reasons for its development, a description of the seven modules, and the findings of a preliminary test of four of the modules for feasibility and credibility. Initially developed in response to a need…

Experimental Testing of a Van De Graaff Generator as an Electromagnetic Pulse Generator

Science.gov (United States)

2016-07-01

EXPERIMENTAL TESTING OF A VAN DE GRAAFF GENERATOR AS AN ELECTROMAGNETIC PULSE GENERATOR THESIS...protection in the United States AFIT-ENP-MS-16-S-075 EXPERIMENTAL TESTING OF A VAN DE GRAAFF GENERATOR AS AN ELECTROMAGNETIC PULSE GENERATOR...RELEASE; DISTRIBUTION UNLIMITED. AFIT-ENP-MS-16-S-075 EXPERIMENTAL TESTING OF A VAN DE GRAAFF GENERATOR AS AN ELECTROMAGNETIC PULSE GENERATOR

The FENIX [Fusion ENgineering International EXperimental] test facility

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Chaplin, M.R.; Miller, J.R.; Shen, S.S.; Summers, L.T.; Kerns, J.A.

1989-01-01

The Fusion ENgineering International EXperimental Magnet Facility (FENIX), under construction at Lawrence Livermore National Laboratory (LLNL), is a significant step forward in meeting the testing requirements necessary for the development of superconductor for large-scale, superconducting magnets. A 14-T, transverse field over a test volume of 150 x 60 x 150 mm in length will be capable of testing conductors the size of the International Thermonuclear Experimental Reactor (ITER). Proposed conductors for ITER measure ∼35 mm on one side and will operate at currents of up to 40 kA at fields of ∼14 T. The testing of conductors and associated components, such as joints, will require large-bore, high-field magnet facilities. FENIX is being constructed using the existing A 2o and A 2i magnets from the idle MFTF. The east and west A 2 pairs will be mounted together to form a split-pair solenoid. The pairs of magnets will be installed in a 4.0-m cryostat vessel located in the HFTF building at LLNL. Each magnet is enclosed in its own cryostat, the existing 4.0-m vessel serving only as a vacuum chamber. 4 refs., 8 figs

Cost-effective degradation test plan for a nonlinear random-coefficients model

International Nuclear Information System (INIS)

Kim, Seong-Joon; Bae, Suk Joo

2013-01-01

The determination of requisite sample size and the inspection schedule considering both testing cost and accuracy has been an important issue in the degradation test. This paper proposes a cost-effective degradation test plan in the context of a nonlinear random-coefficients model, while meeting some precision constraints for failure-time distribution. We introduce a precision measure to quantify the information losses incurred by reducing testing resources. The precision measure is incorporated into time-varying cost functions to reflect real circumstances. We apply a hybrid genetic algorithm to general cost optimization problem with reasonable constraints on the level of testing precision in order to determine a cost-effective inspection scheme. The proposed method is applied to the degradation data of plasma display panels (PDPs) following a bi-exponential degradation model. Finally, sensitivity analysis via simulation is provided to evaluate the robustness of the proposed degradation test plan.

Test plan for core sampling drill bit temperature monitor

International Nuclear Information System (INIS)

Francis, P.M.

1994-01-01

At WHC, one of the functions of the Tank Waste Remediation System division is sampling waste tanks to characterize their contents. The push-mode core sampling truck is currently used to take samples of liquid and sludge. Sampling of tanks containing hard salt cake is to be performed with the rotary-mode core sampling system, consisting of the core sample truck, mobile exhauster unit, and ancillary subsystems. When drilling through the salt cake material, friction and heat can be generated in the drill bit. Based upon tank safety reviews, it has been determined that the drill bit temperature must not exceed 180 C, due to the potential reactivity of tank contents at this temperature. Consequently, a drill bit temperature limit of 150 C was established for operation of the core sample truck to have an adequate margin of safety. Unpredictable factors, such as localized heating, cause this buffer to be so great. The most desirable safeguard against exceeding this threshold is bit temperature monitoring . This document describes the recommended plan for testing the prototype of a drill bit temperature monitor developed for core sampling by Sandia National Labs. The device will be tested at their facilities. This test plan documents the tests that Westinghouse Hanford Company considers necessary for effective testing of the system

Statistical analysis and planning of multihundred-watt impact tests

International Nuclear Information System (INIS)

Martz, H.F. Jr.; Waterman, M.S.

1977-10-01

Modular multihundred-watt (MHW) radioisotope thermoelectric generators (RTG's) are used as a power source for spacecraft. Due to possible environmental contamination by radioactive materials, numerous tests are required to determine and verify the safety of the RTG. There are results available from 27 fueled MHW impact tests regarding hoop failure, fingerprint failure, and fuel failure. Data from the 27 tests are statistically analyzed for relationships that exist between the test design variables and the failure types. Next, these relationships are used to develop a statistical procedure for planning and conducting either future MHW impact tests or similar tests on other RTG fuel sources. Finally, some conclusions are given

AZ-101 Mixer Pump Demonstration and Tests Data Management Analysis Plan

Energy Technology Data Exchange (ETDEWEB)

DOUGLAS, D.G.

2000-02-22

This document provides a plan for the analysis of the data collected during the AZ-101 Mixer Pump Demonstration and Tests. This document was prepared after a review of the AZ-101 Mixer Pump Test Plan (Revision 4) [1] and other materials. The plan emphasizes a structured and well-ordered approach towards handling and examining the data. This plan presumes that the data will be collected and organized into a unified body of data, well annotated and bearing the date and time of each record. The analysis of this data will follow a methodical series of steps that are focused on well-defined objectives. Section 2 of this plan describes how the data analysis will proceed from the real-time monitoring of some of the key sensor data to the final analysis of the three-dimensional distribution of suspended solids. This section also identifies the various sensors or sensor systems and associates them with the various functions they serve during the test program. Section 3 provides an overview of the objectives of the AZ-101 test program and describes the data that will be analyzed to support that test. The objectives are: (1) to demonstrate that the mixer pumps can be operated within the operating requirements; (2) to demonstrate that the mixer pumps can mobilize the sludge in sufficient quantities to provide feed to the private contractor facility, and (3) to determine if the in-tank instrumentation is sufficient to monitor sludge mobilization and mixer pump operation. Section 3 also describes the interim analysis that organizes the data during the test, so the analysis can be more readily accomplished. Section 4 describes the spatial orientation of the various sensors in the tank. This section is useful in visualizing the relationship of the Sensors in terms of their location in the tank and how the data from these sensors may be related to the data from other sensors. Section 5 provides a summary of the various analyses that will be performed on the data during the test

AZ-101 Mixer Pump Demonstration and Tests: Data Management (Analysis) Plan

International Nuclear Information System (INIS)

DOUGLAS, D.G.

2000-01-01

This document provides a plan for the analysis of the data collected during the AZ-101 Mixer Pump Demonstration and Tests. This document was prepared after a review of the AZ-101 Mixer Pump Test Plan (Revision 4) [1] and other materials. The plan emphasizes a structured and well-ordered approach towards handling and examining the data. This plan presumes that the data will be collected and organized into a unified body of data, well annotated and bearing the date and time of each record. The analysis of this data will follow a methodical series of steps that are focused on well-defined objectives. Section 2 of this plan describes how the data analysis will proceed from the real-time monitoring of some of the key sensor data to the final analysis of the three-dimensional distribution of suspended solids. This section also identifies the various sensors or sensor systems and associates them with the various functions they serve during the test program. Section 3 provides an overview of the objectives of the AZ-101 test program and describes the data that will be analyzed to support that test. The objectives are: (1) to demonstrate that the mixer pumps can be operated within the operating requirements; (2) to demonstrate that the mixer pumps can mobilize the sludge in sufficient quantities to provide feed to the private contractor facility, and (3) to determine if the in-tank instrumentation is sufficient to monitor sludge mobilization and mixer pump operation. Section 3 also describes the interim analysis that organizes the data during the test, so the analysis can be more readily accomplished. Section 4 describes the spatial orientation of the various sensors in the tank. This section is useful in visualizing the relationship of the Sensors in terms of their location in the tank and how the data from these sensors may be related to the data from other sensors. Section 5 provides a summary of the various analyses that will be performed on the data during the test

The Unified Language Testing Plan: Speaking Proficiency Test. Spanish and English Pilot Validation Studies. Report Number 1.

Science.gov (United States)

Thornton, Julie A.

This report describes one segment of the Federal Language Testing Board's Unified Language Testing Plan (ULTP), the validation of speaking proficiency tests in Spanish and English. The ULTP is a project to increase standardization of foreign language proficiency measurement and promote sharing of resources among testing programs in the federal…

Environmental Monitoring Plan, Nevada Test Site and support facilities

International Nuclear Information System (INIS)

1991-11-01

This Environmental Monitoring Plan applies to the US Department of Energy's (DOE's) operations on the Continental US (including Amchitka Island, Alaska) that are under the purview of the DOE Nevada Field Office (DOE/NV). The primary purpose of these operations is the conduct of the nuclear weapons testing program for the DOE and the Department of Defense. Since 1951, these tests have been conducted principally at the Nevada Test Site (NTS), which is located approximately 100 miles northwest of Las Vegas, Nevada. In accordance with DOE Order 5400.1, this Environmental Monitoring Plan brings together in one document a description of the environmental activities conducted at the NTS by user organizations, operations support contractors, and the US Environmental Protection Agency (EPA). The EPA conducts both the offsite environmental monitoring program around the NTS and post-operational monitoring efforts at non-NTS test locations used between 1961 and 1973 in other parts of the continental US. All of these monitoring activities are conducted under the auspices of the DOE/NV, which has the stated policy of conducting its operations in compliance with both the letter and the spirit of applicable environmental statutes, regulations, and standards

Test plan for K-Basin fuel handling tools

International Nuclear Information System (INIS)

Bridges, A.E.

1995-01-01

The purpose of this document is to provide the test plan and procedures for the acceptance testing of the handling tools enveloped for the removal of an N-Reactor fuel element from its storage canister in the K-Basins storage pool and insertion into the Single fuel Element Can for subsequent shipment to a Hot Cell for examination. Examination of these N-Reactor fuel elements is part of the overall characterization effort. New hand tools were required since previous fuel movement has involved grasping the fuel in a horizontal position. The 305 Building Cold Test Facility will be used to conduct the acceptance testing of the Fuel Handling Tools. Upon completion of this acceptance testing and any subsequent training of operators, the tools will be transferred to the 105 KW Basin for installation and use

Test plan: Gas-threshold-pressure testing of the Salado Formation in the WIPP underground facility

International Nuclear Information System (INIS)

Saulnier, G.J. Jr.

1992-03-01

Performance assessment for the disposal of radioactive waste from the United States defense program in the WIPP underground facility must assess the role of post-closure was generation by waste degradation and the subsequent pressurization of the facility. be assimilated by the host formation will Whether or not the generated gas can be assimilated by the host formation will determine the ability of the gas to reach or exceed lithostatic pressure within the repository. The purpose of this test plan is (1) to present a test design to obtain realistic estimates of gas-threshold pressure for the Salado Formation WIPP underground facility including parts of the formation disturbed by the underground of the Salado, and (2) to provide a excavations and in the far-field or undisturbed part framework for changes and amendments to test objectives, practices, and procedures. Because in situ determinations of gas-threshold pressure in low-permeability media are not standard practice, the methods recommended in this testplan are adapted from permeability-testing and hydrofracture procedures. Therefore, as the gas-threshold-pressure testing program progresses, personnel assigned to the program and outside observers and reviewers will be asked for comments regarding the testing procedures. New and/or improved test procedures will be documented as amendments to this test plan, and subject to similar review procedures

Draft Test Plan for Brine Migration Experimental Studies in Run-of-Mine Salt Backfill

Energy Technology Data Exchange (ETDEWEB)

Jordan, Amy B. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Stauffer, Philip H. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Reed, Donald T. [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Boukhalfa, Hakim [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Caporuscio, Florie Andre [Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Robinson, Bruce Alan [Los Alamos National Lab. (LANL), Los Alamos, NM (United States)

2015-02-02

The primary objective of the experimental effort described here is to aid in understanding the complex nature of liquid, vapor, and solid transport occurring around heated nuclear waste in bedded salt. In order to gain confidence in the predictive capability of numerical models, experimental validation must be performed to ensure that (a) hydrological and physiochemical parameters and (b) processes are correctly simulated. The experiments proposed here are designed to study aspects of the system that have not been satisfactorily quantified in prior work. In addition to exploring the complex coupled physical processes in support of numerical model validation, lessons learned from these experiments will facilitate preparations for larger-scale experiments that may utilize similar instrumentation techniques.

Minnesota urban partnership agreement national evaluation : telecommuting test plan.

Science.gov (United States)

2009-11-17

This report presents the telecommuting test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employing str...

The FELIX experimental program and future upgrades

International Nuclear Information System (INIS)

Turner, L.R.; Praeg, W.F.; Lari, R.J.; Wehrle, R.B.

1981-01-01

As part of the DOE First Wall/Blanket/Shield (FW/B/S) Engineering Test Program, Argonne National Laboratory FELIX (Fusion ELectromagnetic Induction EXperiment to study electromagnetic effects. T.he earliest test will select and verify appropriate eddy current simulation computer program (codes), followed by component concept tests, component model tests, and finally tests with prototypes. This paper describes the experimental and computer code plans and future upgrades for the FELIX facility

Minnesota urban partnership agreement national evaluation : tolling test plan.

Science.gov (United States)

2009-11-17

This report presents the test plan for collecting and analyzing toll data for the Minnesota Urban Partnership : Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The : Minnesota UPA projects focus on reducin...

The effect of a career activity on the students' perception of the nursing profession and their career plan: A single-group experimental study.

Science.gov (United States)

Yilmaz, Arzu Akman; Ilce, Arzu; Can Cicek, Saadet; Yuzden, Ganime Esra; Yigit, Ummuhan

2016-04-01

Students' conceptualizations of nursing and their reasons for choosing the profession motivate them and affect their education, work performance and career plans. Nursing educators should support them to plan their careers consciously during their education. The study aimed to investigate the effect of career-planning event for nursing students on their conceptualizations of the nursing profession and their career plans. The study was as single-group experimental study using a pre-test and post-test. The career-planning event was held in the conference hall of the university involved in the current study, and was open to the all students of the nursing school. The sample of the study consisted of 105 students who participated in the "Nursing Career Symposium" held on 27 March 2015. Methods At the event, the importance of career planning and the opportunities of the nursing profession was presented. The data were collected using a questionnaire consisted of two sections including descriptive characteristics and the opinions of the students regarding their career plans and Perception of Nursing Profession Scale. The students completed the first section of the questionnaire before the career event began and the second section of the questionnaire and scale both before and after the event. The participants had positive conceptualizations of the profession. Following a career event, the participants' opinions of professional qualities and professional status as measured through the Perception of Nursing Profession Scale showed a significant increase, and that the event had made an important contribution to their career plans. In the light of these results, it is possible to suggest that such events have an important place during education in that they introduce the nursing profession, and they develop the students' positive thoughts regarding the profession in terms of both course content and teaching methodology. Copyright © 2016 Elsevier Ltd. All rights reserved.

Experimental Program for the CLIC test facility 3 test beam line

CERN Document Server

Adli, E; Dobert, S; Olvegaard, M; Schulte, D; Syratchev, I; Lillestol, Reidar

2010-01-01

The CLIC Test Facility 3 Test Beam Line is the first prototype for the CLIC drive beam decelerator. Stable transport of the drive beam under deceleration is a mandatory component in the CLIC two-beam scheme. In the Test Beam Line more than 50% of the total energy will be extracted from a 150 MeV, 28 A electron drive beam, by the use of 16 power extraction and transfer structures. A number of experiments are foreseen to investigate the drive beam characteristics under deceleration in the Test Beam Line, including beam stability, beam blow up and the efficiency of the power extraction. General benchmarking of decelerator simulation and theory studies will also be performed. Specially designed instrumentation including precision BPMs, loss monitors and a time-resolved spectrometer dump will be used for the experiments. This paper describes the experimental program foreseen for the Test Beam Line, including the relevance of the results for the CLIC decelerator studies.

Updated FY12 Ceramic Fuels Irradiation Test Plan

International Nuclear Information System (INIS)

Nelson, Andrew T.

2012-01-01

The Fuel Cycle Research and Development program is currently devoting resources to study of numerous fuel types with the aim of furthering understanding applicable to a range of reactors and fuel cycles. In FY11, effort within the ceramic fuels campaign focused on planning and preparation for a series of rabbit irradiations to be conducted at the High Flux Isotope Reactor located at Oak Ridge National Laboratory. The emphasis of these planned tests was to study the evolution of thermal conductivity in uranium dioxide and derivative compositions as a function of damage induced by neutron damage. Current fiscal realities have resulted in a scenario where completion of the planned rabbit irradiations is unlikely. Possibilities for execution of irradiation testing within the ceramic fuels campaign in the next several years will thus likely be restricted to avenues where strong synergies exist both within and outside the Fuel Cycle Research and Development program. Opportunities to augment the interests and needs of modeling, advanced characterization, and other campaigns present the most likely avenues for further work. These possibilities will be pursued with the hope of securing future funding. Utilization of synthetic microstructures prepared to better understand the most relevant actors encountered during irradiation of ceramic fuels thus represents the ceramic fuel campaign's most efficient means to enhance understanding of fuel response to burnup. This approach offers many of the favorable attributes embraced by the Separate Effects Testing paradigm, namely production of samples suitable to study specific, isolated phenomena. The recent success of xenon-imbedded thick films is representative of this approach. In the coming years, this strategy will be expanded to address a wider range of problems in conjunction with use of national user facilities novel characterization techniques to best utilize programmatic resources to support a science-based research program.

Specification and acceptance testing of radiotherapy treatment planning systems

International Nuclear Information System (INIS)

2007-04-01

Quality assurance (QA) in the radiation therapy treatment planning process is essential to ensure accurate dose delivery to the patient and to minimize the possibility of accidental exposure. The computerized radiotherapy treatment planning systems (RTPSs) are now widely available in industrialized and developing countries and it is of special importance to support hospitals in Member States in developing procedures for acceptance testing, commissioning and QA of their RTPSs. Responding to these needs, a group of experts developed an IAEA publication with such recommendations, which was published in 2004 as IAEA Technical Reports Series No. 430. This report provides a general framework and describes a large number of tests and procedures that should be considered by the users of new RTPSs. However, small hospitals with limited resources or large hospitals with high patient load and limited staff are not always able to perform complete characterization, validation and software testing of algorithms used in RTPSs. Therefore, the IAEA proposed more specific guidelines that provide a step-by-step recommendation for users at hospitals or cancer centres how to implement acceptance and commissioning procedures for newly purchased RTPSs. The current publication was developed in the framework of the Coordinated Research Project on Development of Procedures for Quality Assurance for Dosimetry Calculations in Radiotherapy and uses the International Electrotechnical Commission (IEC) standard IEC 62083, Requirements for the Safety of Radiotherapy Treatment Planning Systems as its basis. The report addresses the procedures for specification and acceptance testing of RTPSs to be used by both manufacturers and users at the hospitals. Recommendations are provided for specific tests to be performed at the manufacturing facility known as type tests, and for acceptance tests to be performed at the hospital known as site tests. The purpose of acceptance testing is to demonstrate to the

A Test of Motor (Not Executive) Planning in Developmental Coordination Disorder and Autism

NARCIS (Netherlands)

van Swieten, Lisa M.; van Bergen, Elsje; Williams, Justin H G; Wilson, Andrew D.; Plumb, Mandy S.; Kent, Samuel W.; Mon-Williams, Mark A.

Grip selection tasks have been used to test "planning" in both autism and developmental coordination disorder (DCD). We differentiate between motor and executive planning and present a modified motor planning task. Participants grasped a cylinder in 1 of 2 orientations before turning it clockwise or

A test of motor (not executive) planning in developmental coordination disorder and autism

NARCIS (Netherlands)

van Swieten, L.M.; van Bergen, E.; Williams, J.H.G.; Wilson, A.D.; Plumb, M.S.; Kent, S.W.; Mon-Williams, M.A.

2010-01-01

Grip selection tasks have been used to test "planning" in both autism and developmental coordination disorder (DCD). We differentiate between motor and executive planning and present a modified motor planning task. Participants grasped a cylinder in 1 of 2 orientations before turning it clockwise or

Care plans using concept maps and their effects on the critical thinking dispositions of nursing students.

Science.gov (United States)

Atay, Selma; Karabacak, Ukke

2012-06-01

It is expected that nursing education improves abilities of students in solving problems, decision making and critical thinking in different circumstances. This study was performed to analyse the effects of care plans prepared using concept maps on the critical thinking dispositions of students. An experimental group and a control group were made up of a total of 80 freshman and sophomore students from the nursing department of a health school. The study used a pre-test post-test control group design. The critical thinking dispositions of the groups were measured using the California Critical Thinking Disposition Inventory. In addition, the care plans prepared by the experimental group students were evaluated using the criteria for evaluating care plans with concept maps. T-test was used in analysing the data. The results showed that there were no statistically significant differences in the total and sub-scale pre-test scores between the experimental group and control group students. There were also significant differences in the total and sub-scale post-test scores between the experimental group and control group students. There were significant differences between concept map care plan evaluation criteria mean scores of the experimental students. In the light of these findings, it could be argued that the concept mapping strategy improves critical thinking skills of students. © 2012 Blackwell Publishing Asia Pty Ltd.

Sustainable land use planning at the Semipalatinsk Nuclear Test Site

International Nuclear Information System (INIS)

Coughtrey, P.J.; Ridgway, R.B.; Baumann, P.

2001-01-01

Full text: The UK Department for International Development (DFID) has recently agreed to support a project to develop a participatory sustainable land use plan for areas affected by nuclear weapons testing at Semipalatinsk. This three year project is expected to be initiated in April 2001 and will form one component of the United Nations Development Programme (UNDP) Semipalatinsk Rehabilitation Programme. The project will be undertaken by a combination of Kazakh organizations working with UK consultants and will meet its overall aim through the following main activities: Development of institutional capacity in data management and analysis; Provision of information and education on environmental contamination, hazards and risks; Development of a participatory land use planning process and piloting of the process in specific areas and communities around the test site; Integration of mineral resource extraction in the land planning process with a focus- on water resource and environmental protection and participatory approaches to resolving land use conflicts; Development of legislative tools to permit the implementation of environmental management of resource exploitation. The project will make use of both modern satellite-based imagery and more traditional methods to determine the potential for different land uses within the test site. The results obtained will be incorporated with additional information on land use. radiological and hydrological conditions at the test site through a geographical information system (GIS) provided by the project. The GIS will form the core component for collation and distribution of information on options available for use of different areas of the test site and its vicinity. A participatory rural appraisal, using tried and tested techniques, will identify local interest groups in land use planning and identify the details of their stake in the process. The groups will include owners-herders, employee-herders, and subsistence

Dosimetric accuracy of a treatment planning system for actively scanned proton beams and small target volumes: Monte Carlo and experimental validation

CERN Document Server

Magro, G; Mairani, A; Mirandola, A; Panizza, D; Russo, S; Ferrari, A; Valvo, F; Fossati, P; Ciocca, M

2015-01-01

This study was performed to evaluate the accuracy of a commercial treatment planning system (TPS), in optimising proton pencil beam dose distributions for small targets of different sizes (5–30 mm side) located at increasing depths in water. The TPS analytical algorithm was benchmarked against experimental data and the FLUKA Monte Carlo (MC) code, previously validated for the selected beam-line. We tested the Siemens syngo® TPS plan optimisation module for water cubes fixing the configurable parameters at clinical standards, with homogeneous target coverage to a 2 Gy (RBE) dose prescription as unique goal. Plans were delivered and the dose at each volume centre was measured in water with a calibrated PTW Advanced Markus® chamber. An EBT3® film was also positioned at the phantom entrance window for the acquisition of 2D dose maps. Discrepancies between TPS calculated and MC simulated values were mainly due to the different lateral spread modeling and resulted in being related to the field-to-spot size r...

In situ gas treatment technology demonstration test plan

International Nuclear Information System (INIS)

Thornton, E.C.; Miller, R.D.

1996-01-01

This document defines the objectives and requirements associated with undertaking a field demonstration of an in situ gas treatment appoach to remediation chromate-contaminated soil. The major tasks presented in this plan include the design and development of the surface gas treatment system, performance of permitting activities, and completion of site preparation and field testing activities

Radioactive waste isolation in salt: Peer review of the Golder Associates draft test plan for in situ testing in an exploratory shaft in salt

International Nuclear Information System (INIS)

Hambley, D.F.; Mraz, D.Z.; Unterberter, R.R.

1987-01-01

This report documents the peer review conducted by Argonne National Laboratory of a document entitled ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared for Battelle Memorial Institute's Office of Nuclear Waste Isolation by Golder Associates, Inc. In general, the peer review panelists found the test plan to be technically sound, although some deficiencies were identified. Recommendations for improving the test plan are presented in this review report. A microfiche copy of the following unpublished report is attached to the inside back cover of this report: ''Draft Test Plan for In Situ Testing in an Exploratory Shaft in Salt,'' prepared by Golder Associates, Inc., for Office of Nuclear Waste Isolation, Battelle Memorial Institute, Columbus, Ohio (March 1985)

International Thermonuclear Experimental Reactor U.S. Home Team Quality Assurance Plan

Energy Technology Data Exchange (ETDEWEB)

Sowder, W. K.

1998-10-01

The International Thermonuclear Experimental Reactor (ITER) project is unique in that the work is divided among an international Joint Central Team and four Home Teams, with the overall responsibility for the quality of activities performed during the project residing with the ITER Director. The ultimate responsibility for the adequacy of work performed on tasks assigned to the U.S. Home Team resides with the U.S. Home Team Leader and the U.S. Department of Energy Office of Fusion Energy (DOE-OFE). This document constitutes the quality assurance plan for the ITER U.S. Home Team. This plan describes the controls exercised by U.S. Home Team management and the Performing Institutions to ensure the quality of tasks performed and the data developed for the Engineering Design Activities assigned to the U.S. Home Team and, in particular, the Research and Development Large Projects (7). This plan addresses the DOE quality assurance requirements of 10 CFR 830.120, "Quality Assurance." The plan also describes U.S. Home Team quality commitments to the ITER Quality Assurance Program. The ITER Quality Assurance Program is based on the principles described in the International Atomic Energy Agency Standard No. 50-C-QA, "Quality Assurance for Safety in Nuclear Power Plants and Other Nuclear Facilities." Each commitment is supported with preferred implementation methodology that will be used in evaluating the task quality plans to be submitted by the Performing Institutions. The implementing provisions of the program are based on guidance provided in American National Standards Institute/American Society of Mechanical Engineers NQA-1 1994, "Quality Assurance." The individual Performing Institutions will implement the appropriate quality program provisions through their own established quality plans that have been reviewed and found to comply with U.S. Home Team quality assurance plan commitments to the ITER Quality Assurance Program. The extent of quality program provisions

Evaluation tests of treatment planning systems concerning 3D dose calculation

International Nuclear Information System (INIS)

Simonian-Sauve, M.; Smart, C.

1998-01-01

The development of irradiation techniques in radiotherapy shows a clear tendency towards the systematic use of three-dimensional (3D) information. Great efforts are being made to set up 3D conformal radiotherapy. Consequently, in the aim of greater coherence and accuracy, 'the dosimetric tool' must also meet the requirements of 3D radiotherapy, as it plays a role in the treatment chain. To know if the treatment planning system is a '3D', '2D', or even '1D' system, one should not be satisfied with reading the technical documentation and the program algorithm description not entirely trust the constructor's assertions. It is essential to clearly and precisely evaluate the possibilities of the treatment planning system. Even if it is proved not to satisfy perfectly all the tests which would qualify it as a real 3D calculation system, the study of the test results helps to give clear explanations of the dosimetric results. Two series of test cases are proposed. The first series allows us to understand in which conditions the treatment planning system takes into account the scatter influence in a volume. The second series is designed to inform us about the capacity of the dose calculation algorithm when the medium encloses non-homogeneities. These test cases do not constitute an exhaustive 'check-list' able to tackle completely the question of 3D calculation. They are submitted as examples and should be considered as an evaluation methodology for the software implanted in the treatment planning system. (authors)

Motivation and performance in physical education: an experimental test.

Science.gov (United States)

Moreno, Juan A; González-Cutre, David; Martín-Albo, José; Cervelló, Eduardo

2010-01-01

The purpose of this study was to analyse, experimentally, the relationships between motivation and performance in a lateral movement test in physical education. The study group consisted of 363 students (227 boys and 136 girls), aged between 12 and 16, who were randomly divided into three groups: an experimental group in which an incremental ability belief was induced, another experimental group in which an entity ability belief was induced, and a control group where there was no intervention. Measurements were made of situational intrinsic motivation, perceived competence in executing the task and performance. The results revealed that the incremental group reported higher scores on the situational intrinsic motivation scale. The entity group demonstrated better performance in the first test attempt than the incremental group but, in the second attempt, the performance was similar in the different groups. Perhaps the initial differences in performance disappeared because the incremental group counted on improving in the second attempt. These results are discussed in relation to the intensity with which the teacher conveys information relating to incremental ability belief of the pupil to increase intrinsic motivation and performance. Key pointsThe incremental group showed more situational intrinsic motivation.The entity group showed higher performance in the first test attempt, but significant differences disappeared in the second attempt.It seems that this incremental belief and greater intrinsic motivation made the students trust they would improve their performance in the second attempt at the lateral movement test.

Computer-aided dispatch--traffic management center field operational test final detailed test plan : WSDOT deployment

Science.gov (United States)

2003-10-01

The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : WSDOT deployment". This document defines the objective, approach,...

MSFC Doppler Lidar Science experiments and operations plans for 1981 airborne test flight

Science.gov (United States)

Fichtl, G. H.; Bilbro, J. W.; Kaufman, J. W.

1981-01-01

The flight experiment and operations plans for the Doppler Lidar System (DLS) are provided. Application of DLS to the study of severe storms and local weather penomena is addressed. Test plans involve 66 hours of flight time. Plans also include ground based severe storm and local weather data acquisition.

Project W-314 specific test and evaluation plan for 241-AN-A valve pit

International Nuclear Information System (INIS)

Hays, W.H.

1997-01-01

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made to the 241-AN-A Valve Pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a ''lower tier'' document based on the W-314 Test and Evaluation Plan (TEP) This STEP encompasses all testing activities required to demonstrate compliance to the project design criteria as it relates to the modifications of the AN-A valve pit. The Project Design Specifications (PDS) identify the specific testing activities required for the Project. Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities), Factory Acceptance Tests (FATs), installation tests and inspections, Construction Acceptance Tests (CATs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). It should be noted that POTPs are not required for testing of the modifications to the 241-AN-A Valve Pit. The STEP will be utilized in conjunction with the TEP for verification and validation

An Overview of the NASA Aeronautics Test Program Strategic Plan

Science.gov (United States)

Marshall, Timothy J.

2010-01-01

U.S. leadership in aeronautics depends on ready access to technologically advanced, efficient, and affordable aeronautics test capabilities. These systems include major wind tunnels and propulsion test facilities and flight test capabilities. The federal government owns the majority of the major aeronautics test capabilities in the United States, primarily through the National Aeronautics and Space Administration (NASA) and the Department of Defense (DoD), however an overarching strategy for management of these national assets was needed. Therefore, in Fiscal Year (FY) 2006 NASA established the Aeronautics Test Program (ATP) as a two-pronged strategic initiative to: (1) retain and invest in NASA aeronautics test capabilities considered strategically important to the agency and the nation, and (2) establish a strong, high level partnership with the DoD Test Resources Management Center (TRMC), stewards of the DoD test and evaluation infrastructure. Since then, approximately seventy percent of the ATP budget has been directed to underpin fixed and variable costs of facility operations within its portfolio and the balance towards strategic investments in its test facilities, including maintenance and capability upgrades. Also, a strong guiding coalition was established through the National Partnership for Aeronautics Testing (NPAT), with governance by the senior leadership of NASA s Aeronautics Research Mission Directorate (ARMD) and the DoD's TRMC. As part of its strategic planning, ATP has performed or participated in many studies and analyses, including assessments of major NASA and DoD aeronautics test capabilities, test facility condition evaluations and market research. The ATP strategy has also benefitted from unpublished RAND research and analysis by Ant n et al. (2009). Together, these various studies, reports and assessments serve as a foundation for a new, five year strategic plan that will guide ATP through FY 2014. Our vision for the future is a balanced

C-018H LERF filtration test plan. Revision 1

International Nuclear Information System (INIS)

Moberg, T.P.; King, C.V.

1994-01-01

The following outlines the plan to test the polymeric backwash filtration system at the LERF. These tests will determine if the ETF filter design is adequate. If the tests show that the design is adequate, the task will be complete. If the tests show that the technology is inadequate, it may be necessary to perform further tests to qualify other candidate filtration technologies (e.g., polymeric tubular ultrafiltration, centrifugal ultrafiltration). The criteria to determine the success or failure of the backwash filter will be based on the system's ability to remove the bacteria and inorganic contaminants from the evaporator process condensate. The tests are designed to qualify the design basis of the filtration technology that will be used in the ETF

C-018H LERF filtration test plan. Revision 1

Energy Technology Data Exchange (ETDEWEB)

Moberg, T.P.; King, C.V.

1994-08-26

The following outlines the plan to test the polymeric backwash filtration system at the LERF. These tests will determine if the ETF filter design is adequate. If the tests show that the design is adequate, the task will be complete. If the tests show that the technology is inadequate, it may be necessary to perform further tests to qualify other candidate filtration technologies (e.g., polymeric tubular ultrafiltration, centrifugal ultrafiltration). The criteria to determine the success or failure of the backwash filter will be based on the system`s ability to remove the bacteria and inorganic contaminants from the evaporator process condensate. The tests are designed to qualify the design basis of the filtration technology that will be used in the ETF.

The experimental plan of displacement- and frequency-noise free laser interferometer

International Nuclear Information System (INIS)

Kokeyama, K; Sato, S; Kawamura, S; Nishizawa, A; Chen, Y; Pai, A; Somiya, K; Ward, R; Sugamoto, A

2008-01-01

We present the partial demonstration of displacement- and laser-noise free interferometer (DFI) and the next experimental plan to examine the complete configuration. A part of the full implementation of DFI has been demonstrated to confirm the cancellation of beamsplitter displacements. The displacements were suppressed by about two orders of magnitude. The aim of the next experiment is to operate the system and to confirm the cancellation of all displacement noises, while the gravitational wave (GW) signals survive. The optical displacements will be simulated by electro-optic modulators (EOM). To simulate the GW contribution to laser lights, we will use multiple EOMs

Testing methods of ECR ion source experimental platform

International Nuclear Information System (INIS)

Zhou Changgeng; Hu Yonghong; Li Yan

2006-12-01

The principle and structure of ECR ion source experimental platform were introduce. The testing methods of the parameters of single main component and the comprehensive parameters under the condition of certain beam current and beam spot diameter were summarized in process of manufacturing. Some appropriate testing dates were given. The existent questions (the parameters of plasma density in discharge chamber and accurate hydrogen flow, etc. can not be measured in operation) and resolutions were also put forward. (authors)

The endowment effect and WTA: a quasi-experimental test

Science.gov (United States)

H.F. MacDonald; J. Michael Bowker

1993-01-01

This paper reports a test of the endowment effect in an economic analysis of localized air pollution. Regression techniques are used to test the significance of perceived property rights on household WTP for improved air quality versus WTA compensation to forgo an improvement in air quality. Our experimental contributes to the research into WTP/WTA divergence by...

In Situ Vitrification Engineering-Scale Test ES-INEL-4, ES-INEL-5, ES-INEL-6, and ES-INEL-7 Test Plan

International Nuclear Information System (INIS)

Weidner, J.R.; Stoots, P.R.

1990-10-01

The In Situ Vitrification Engineering-Scale Tests ES-4, ES-5, ES-6, and ES-7 Product Characterization Test Plan describes the methods and procedures to be used or the physical and chemical characterization of the solid product(s) resulting from the Idaho National Engineering Laboratory engineering scale in situ vitrification tests ES-4, ES-5, ES-6, and ES-7. The goals of this Test Plan are to insure that the product characterization results are sufficient to meet the data needs of the In Situ Vitrification Program and are technically and legally defensible. Important issues addressed by the test plan include sampling and analysis strategy, sampling procedures, laboratory analysis, sample control and document management, equipment, data reporting and validation, quality assurance, specific routine procedures to assess data representativeness, safety and training program, and data management. 9 refs., 1 fig., 3 tabs

New experimental proposals for testing Dirac equation

International Nuclear Information System (INIS)

Camacho, Abel; Macias, Alfredo

2004-01-01

The advent of phenomenological quantum gravity has ushered us in the search for experimental tests of the deviations from general relativity predicted by quantum gravity or by string theories, and as a by-product of this quest the possible modifications that some field equations, for instance, the motion equation of spin-1/2-particles, have already been considered. In the present Letter a modified Dirac equation, whose extra term embraces a second-order time derivative, is taken as mainstay, and three different experimental proposals to detect it are put forward. The novelty in these ideas is that two of them do not fall within the extant approaches in this context, to wit, red-shift, atomic interferometry, or Hughes-Drever type-like experiments

Test plan for evaluating the performance of the in-tank fluidic sampling system

International Nuclear Information System (INIS)

BOGER, R.M.

1999-01-01

The PHMC will provide Low Activity Wastes (LAW) tank wastes for final treatment by a privatization contractor from double-shell feed tanks, 241-AP-102 and 241-AP-104, Concerns about the inability of the baseline ''grab'' sampling to provide large volume samples within time constraints has led to the development of a conceptual sampling system that would be deployed in a feed tank riser, This sampling system will provide large volume, representative samples without the environmental, radiation exposure, and sample volume impacts of the current base-line ''grab'' sampling method. This test plan identifies ''proof-of-principle'' cold tests for the conceptual sampling system using simulant materials. The need for additional testing was identified as a result of completing tests described in the revision test plan document, Revision 1 outlines tests that will evaluate the performance and ability to provide samples that are representative of a tanks' content within a 95 percent confidence interval, to recovery from plugging, to sample supernatant wastes with over 25 wt% solids content, and to evaluate the impact of sampling at different heights within the feed tank. The test plan also identifies operating parameters that will optimize the performance of the sampling system

Computer-aided dispatch--traffic management center field operational test final test plans : state of Utah

Science.gov (United States)

2004-01-01

The purpose of this document is to expand upon the evaluation components presented in "Computer-aided dispatch--traffic management center field operational test final evaluation plan : state of Utah". This document defines the objective, approach, an...

SCENARIO PLANNING AS LEARNING

Directory of Open Access Journals (Sweden)

Antonio Lourenço Junior

2010-10-01

Full Text Available Scenario Planning has been increasingly used, from its introduction to the decision process as effective tools to test decisions, and improve performance in a dynamic environment (Chermack, 2005. The purpose of this article is to demonstrate the potential of an experimental Scenario Planning Model to mobilize, encourage and add more content to the organization’s decision making process – mainly with respect to Strategic Plans of two governmental institutions, a pharmaceutical company and a technology education foundation.  This study describes the application stages of a hybrid scenario-planning model – herein referred to as Planning as Learning – via action-research, showing the scenarios resulting from the experiment and describes the main results of an assessment of such practice. In order to do that, two well-established Scenario Planning models (Prospective school and Shell’s model were analyzed. They were used as a reference for the proposition and application of an experimental model in the two study objects. A questionnaire was used to assess the technique impact. It was possible to obtain high levels of reliability. In-depth interviews were also conducted with the participants. At the end, the results confirmed the model efficiency as a basis for decision making in the competitive environment in which the two institutions are inserted, also to encourage the learning process as a group, as observed throughout the work.

SigmaPlot 2000, Version 6.00, SPSS Inc. Computer Software Test Plan

Energy Technology Data Exchange (ETDEWEB)

HURLBUT, S.T.

2000-10-24

SigmaPlot is a vendor software product used in conjunction with the supercritical fluid extraction Fourier transform infrared spectrometer (SFE-FTIR) system. This product converts the raw spectral data to useful area numbers. SigmaPlot will be used in conjunction with procedure ZA-565-301, ''Determination of Moisture by Supercritical Fluid Extraction and Infrared Detection.'' This test plan will be performed in conjunction with or prior to HNF-6936, ''HA-53 Supercritical Fluid Extraction System Acceptance Test Plan'', to perform analyses for water. The test will ensure that the software can be installed properly and will manipulate the analytical data correctly.

Experimental test results of multi-channel test rig of T1 test section, 5

International Nuclear Information System (INIS)

Hino, Ryutaro; Takase, Kazuyuki; Miyamoto, Yoshiaki

1990-09-01

Channel blockage test on a fuel column of the high temperature engineering test reactor (HTTR) has been performed under the helium gas atmosphere at a high temperature and a high pressure in order to obtain safety data on flow rate and temperature distributions in the fuel column with the multi-channel test rig of the fuel stack test section (T 1 ) in HENDEL. In the test, one of 12 fuel channels was blockaded to 90% of flow area at the channel inlet. Experimental results showed that the helium gas flow rate in the blockaded channel was 28%∼33% lower than the average flow rate for Reynolds number from 2300 to 14000 in isothermal flow. When simulated fuel rods were heated, the flow rate in the blockaded channel did not decrease down in comparison with the isothermal flow. This is due to that the heat generated in the fuel rods conducts to the other fuel channels in graphite fuel blocks, so that accelerated pressure losses in the fuel channels change with helium gas temperatures. (author)

Dosimetric accuracy of a treatment planning system for actively scanned proton beams and small target volumes: Monte Carlo and experimental validation

Science.gov (United States)

Magro, G.; Molinelli, S.; Mairani, A.; Mirandola, A.; Panizza, D.; Russo, S.; Ferrari, A.; Valvo, F.; Fossati, P.; Ciocca, M.

2015-09-01

This study was performed to evaluate the accuracy of a commercial treatment planning system (TPS), in optimising proton pencil beam dose distributions for small targets of different sizes (5-30 mm side) located at increasing depths in water. The TPS analytical algorithm was benchmarked against experimental data and the FLUKA Monte Carlo (MC) code, previously validated for the selected beam-line. We tested the Siemens syngo® TPS plan optimisation module for water cubes fixing the configurable parameters at clinical standards, with homogeneous target coverage to a 2 Gy (RBE) dose prescription as unique goal. Plans were delivered and the dose at each volume centre was measured in water with a calibrated PTW Advanced Markus® chamber. An EBT3® film was also positioned at the phantom entrance window for the acquisition of 2D dose maps. Discrepancies between TPS calculated and MC simulated values were mainly due to the different lateral spread modeling and resulted in being related to the field-to-spot size ratio. The accuracy of the TPS was proved to be clinically acceptable in all cases but very small and shallow volumes. In this contest, the use of MC to validate TPS results proved to be a reliable procedure for pre-treatment plan verification.

Dosimetric accuracy of a treatment planning system for actively scanned proton beams and small target volumes: Monte Carlo and experimental validation

International Nuclear Information System (INIS)

Magro, G; Molinelli, S; Mairani, A; Mirandola, A; Panizza, D; Russo, S; Valvo, F; Fossati, P; Ciocca, M; Ferrari, A

2015-01-01

This study was performed to evaluate the accuracy of a commercial treatment planning system (TPS), in optimising proton pencil beam dose distributions for small targets of different sizes (5–30 mm side) located at increasing depths in water. The TPS analytical algorithm was benchmarked against experimental data and the FLUKA Monte Carlo (MC) code, previously validated for the selected beam-line. We tested the Siemens syngo ® TPS plan optimisation module for water cubes fixing the configurable parameters at clinical standards, with homogeneous target coverage to a 2 Gy (RBE) dose prescription as unique goal. Plans were delivered and the dose at each volume centre was measured in water with a calibrated PTW Advanced Markus ® chamber. An EBT3 ® film was also positioned at the phantom entrance window for the acquisition of 2D dose maps. Discrepancies between TPS calculated and MC simulated values were mainly due to the different lateral spread modeling and resulted in being related to the field-to-spot size ratio. The accuracy of the TPS was proved to be clinically acceptable in all cases but very small and shallow volumes. In this contest, the use of MC to validate TPS results proved to be a reliable procedure for pre-treatment plan verification. (paper)

Gearbox Reliability Collaborative Phase 3 Gearbox 3 Test Plan

Energy Technology Data Exchange (ETDEWEB)

Keller, Jonathan [National Renewable Energy Lab. (NREL), Golden, CO (United States); Wallen, Robb [National Renewable Energy Lab. (NREL), Golden, CO (United States)

2016-10-01

This document describes the Phase 3 test plan for the Gearbox Reliability Collaborative Gearbox #3. The primary test objective is to measure the planetary load sharing characteristics in the same conditions as the original gearbox design. If the measured load-sharing characteristics are close to the design model, the projected three-times improvement in planetary section predicted fatigue life and the efficacy of preloaded tapered roller bearings in mitigating the planetary bearing fatigue failure mode will have been demonstrated.

Apparatus and Experimental Procedures to Test Crystal Collimation

CERN Document Server

Montesano, S

2012-01-01

UA9 is an experimental setup operated in the CERN-SPS in view of investigating the feasibility of halo collimation assisted by bent crystals. The test collimation system is composed of one crystal acting as primary halo deflector in the horizontal plane and an absorber. Different crystals are tested in turn using two-arm goniometers with an angular reproducibility of better than 10 microrad. The performance of the system is assessed through the study of the secondary and tertiary halo in critical areas, by using standard machine instrumentation and few customized equipments. The alignment of the crystal is verified by measuring the loss rate close to the crystal position. The collimation efficiency is computed by intercepting the deflected halo with a massive collimator or with an imaging device installed into a Roman Pot. The leakage of the system is evaluated in the dispersion suppressor by means of movable aperture restrictions. In this contribution the setup and the experimental methods in use are revisit...

Project W-314 specific test and evaluation plan for AZ tank farm upgrades

International Nuclear Information System (INIS)

Hays, W.H.

1998-01-01

The purpose of this Specific Test and Evaluation Plan (STEP) is to provide a detailed written plan for the systematic testing of modifications made by the addition of the SN-631 transfer line from the AZ-O1A pit to the AZ-02A pit by the W-314 Project. The STEP develops the outline for test procedures that verify the system's performance to the established Project design criteria. The STEP is a lower tier document based on the W-314 Test and Evaluation P1 an (TEP). Testing includes Validations and Verifications (e.g., Commercial Grade Item Dedication activities, etc), Factory Tests and Inspections (FTIs), installation tests and inspections, Construction Tests and Inspections (CTIs), Acceptance Test Procedures (ATPs), Pre-Operational Test Procedures (POTPs), and Operational Test Procedures (OTPs). The STEP will be utilized in conjunction with the TEP for verification and validation

Adaptive Management Plan for Sensitive Plant Species on the Nevada Test Site

International Nuclear Information System (INIS)

Wills, C. A.

2001-01-01

The Nevada Test Site supports numerous plant species considered sensitive because of their past or present status under the Endangered Species Act and with federal and state agencies. In 1998, the U.S. Department of Energy, Nevada Operation Office (DOE/NV) prepared a Resource Management Plan which commits to protects and conserve these sensitive plant species and to minimize accumulative impacts to them. This document presents the procedures of a long-term adaptive management plan which is meant to ensure that these goals are met. It identifies the parameters that are measured for all sensitive plant populations during long-term monitoring and the adaptive management actions which may be taken if significant threats to these populations are detected. This plan does not, however, identify the current list of sensitive plant species know to occur on the Nevada Test Site. The current species list and progress on their monitoring is reported annually by DOE/NV in the Resource Management Plan

Aboveground Injection Sytem Construction and Mecahnical Integrity Test Plan

Energy Technology Data Exchange (ETDEWEB)

Li, Jun [Sandia National Lab. (SNL-NM), Albuquerque, NM (United States)

2017-10-01

An In-Situ Bioremediation (ISB) Pilot Test Treatability Study is planned at Sandia National Laboratories, New Mexico (SNL/NM) Technical Area-V (TA-V) Groundwater Area of Concern. The Treatability Study is designed to gravity inject an electron-donor substrate and bioaugmentation bacteria into groundwater using an injection well. The constituents of concern (COCs) are nitrate and trichloroethene (TCE). The Pilot Test Treatability Study will evaluate the effectiveness of bioremediation and COC treatment over a prescribed period of time. Results of the pilot test will provide data that will be used to evaluate the cost and effectiveness of a fullscale system.

Hanford Tank Farms Waste Certification Flow Loop Test Plan

Energy Technology Data Exchange (ETDEWEB)

Bamberger, Judith A.; Meyer, Perry A.; Scott, Paul A.; Adkins, Harold E.; Wells, Beric E.; Blanchard, Jeremy; Denslow, Kayte M.; Greenwood, Margaret S.; Morgen, Gerald P.; Burns, Carolyn A.; Bontha, Jagannadha R.

2010-01-01

A future requirement of Hanford Tank Farm operations will involve transfer of wastes from double shell tanks to the Waste Treatment Plant. As the U.S. Department of Energy contractor for Tank Farm Operations, Washington River Protection Solutions anticipates the need to certify that waste transfers comply with contractual requirements. This test plan describes the approach for evaluating several instruments that have potential to detect the onset of flow stratification and critical suspension velocity. The testing will be conducted in an existing pipe loop in Pacific Northwest National Laboratory’s facility that is being modified to accommodate the testing of instruments over a range of simulated waste properties and flow conditions. The testing phases, test matrix and types of simulants needed and the range of testing conditions required to evaluate the instruments are described

Test plan for air monitoring during the Cryogenic Retrieval Demonstration

International Nuclear Information System (INIS)

Yokuda, E.

1992-06-01

This report presents a test plan for air monitoring during the Cryogenic Retrieval Demonstration (CRD). Air monitors will be used to sample for the tracer elements neodymium, terbium, and ytterbium, and dysprosium. The results from this air monitoring will be used to determine if the CRD is successful in controlling dust and minimizing contamination. Procedures and equipment specifications for the test are included

Mixer pump test plan for double shell tank AZ-101

International Nuclear Information System (INIS)

STAEHR, T.W.

1999-01-01

Mixer pump systems have been chosen as the method for retrieval of tank wastes contained in double shell tanks at Hanford. This document describes the plan for testing and demonstrating the ability of two 300 hp mixer pumps to mobilize waste in tank AZ-101. The mixer pumps, equipment and instrumentation to monitor the test were installed by Project W-151

Soil class around me Serpong experimental power reactor (EPR) site plan base on micro tremor data

International Nuclear Information System (INIS)

Marjiyono; Soehaimi A; Hadi Suntoko; Yuliastuti; Syaeful H

2015-01-01

Surface geological characteristics has an important role on site response analysis in a region. In regard with experimental power reactor (EPR) construction plan in Serpong, the subsurface modeling from combination array and single station micro tremor data was done. The array and single station micro tremor measurement were performed in 9 and 90 sites, respectively, at ± 1 km radius around the EPR site plan. The Vs30 value was calculated from shear wave velocity structure around the investigated area. The soil classification based on Vs30 in the investigated area generally consists of SD (medium soil) and SC (soft rock) class. The EPR site plan its self in the SD class region. (author)

118-B-1 excavation treatability test plan

International Nuclear Information System (INIS)

1994-07-01

The Hanford 118-B-1 Burial Ground Treatability Study has been required by milestone change request number-sign M-15-93-04, dated September 30, 1993. The change request requires that a treatability test be conducted at the 100-B Area to obtain additional engineering information for remedial design of burial grounds receiving waste from 100 Area removal actions. This treatability study has two purposes: (1) to support development of the Proposed Plan (PP) and Record of Decision (ROD), which will identify the approach to be used for burial ground remediation, and (2) to provide specific engineering information for receiving waste generated from the 100 Area removal actions. Data generated from this test also will provide critical performance and cost information necessary for remedy evaluation in the detailed analysis of alternatives during preparation of the focused feasibility study (FFS). This treatability testing supports the following 100 Area alternatives: (1) excavation and disposal, and (2) excavation, sorting, (treatment), and disposal

Planning calculations of spray tests for the ERCOSAM-SAMARA project

Energy Technology Data Exchange (ETDEWEB)

Liang, Z. [Atomic Energy of Canada Limited, Chalk River, Ontario (Canada); Andreani, M. [Paul Scherrer Institut, Laboratory for Thermal-Hydraulics, Villigen (Switzerland)

2012-07-01

Within the framework of the ERCOSAM-SAMARA project, co-funded by the European Union and the Russian State Atomic Energy Corporation, planning and pre-test calculations are performed to examine sensitivity parameters that can affect the break-up (erosion) of a helium (substitute for hydrogen) layer by mitigation devices (i.e., cooler, spray, or Passive Autocatalytic Recombiner - PAR). This paper reports the GOTHIC analysis results for the spray tests to be performed in the PANDA facility. The effects of spray flow rate, temperature and injection height on depressurization, erosion of helium cloud and gas transport behavior are studied. This analysis is valuable because only a limited number of conditions will be examined in the planned experiments. The study provides a useful understanding of the interaction of spray with a stratified atmosphere. (author)

Nuclear fuels technologies: Thermally induced gallium removal system (TIGRS), fiscal year 1998 research and development test plan

International Nuclear Information System (INIS)

Buksa, J.J.; Butt, D.P.; Chidester, K.; DeMuth, S.F.; Havrilla, G.J.; James, C.A.; Kolman, D.G.

1997-01-01

This document details the research and development (R and D) activities that will be conducted in Fiscal Year 1998 (FY98) by the Thermally Induced Gallium Removal System (TIGRS) team for the Department of Energy Office of Fissile Materials Disposition. This work is a continuation and extension of experimental activities that have been conducted in support of using weapons-derived plutonium in the fabrication of mixed-oxide (MOX) nuclear fuel for reactor-based plutonium disposition. The ultimate purpose of this work is to demonstrate adequate Thermally Induced Gallium Removal with a prototypic system. This Test Plan presents more than the FY98 R and D efforts in order to frame the Task in its entirety. To achieve the TIGRS Program objectives, R and D activities during the next two years will be focused on (1) process development leading to a prototypic TIGRS design, and (2) prototypic TIGRS design and testing leading to and including a prototypic demonstration of TIGRS operation. Both the process development and system testing efforts will consist of a series of surrogate-based cold tests and plutonium-based hot tests. Some of this testing has already occurred and will continue into FY99

The strong Bell inequalities: A proposed experimental test

Science.gov (United States)

Fry, Edward S.

1994-01-01

All previous experimental tests of Bell inequalities have required additional assumptions. The strong Bell inequalities (i.e. those requiring no additional assumptions) have never been tested. An experiment has been designed that can, for the first time, provide a definitive test of the strong Bell inequalities. Not only will the detector efficiency loophole be closed; but the locality condition will also be rigorously enforced. The experiment involves producing two Hg-199 atoms by a resonant Raman dissociation of a mercury dimer ((199)Hg2) that is in an electronic and nuclear spin singlet state. Bell inequalities can be tested by measuring angular momentum correlations between the spin one-half nuclei of the two Hg-199 atoms. The method used to make these latter measurements will be described.

Experimental method for testing diffraction properties of reflection waveguide holograms.

Science.gov (United States)

Xie, Yi; Kang, Ming-Wu; Wang, Bao-Ping

2014-07-01

Waveguide holograms' diffraction properties include peak wavelength and diffraction efficiency, which play an important role in determining their display performance. Based on the record and reconstruction theory of reflection waveguide holograms, a novel experimental method for testing diffraction properties is introduced and analyzed in this paper, which uses a plano-convex lens optically contacted to the surface of the substrate plate of the waveguide hologram, so that the diffracted light beam can be easily detected. Then an experiment is implemented. The designed reconstruction wavelength of the test sample is 530 nm, and its diffraction efficiency is 100%. The experimental results are a peak wavelength of 527.7 nm and a diffraction efficiency of 94.1%. It is shown that the tested value corresponds well with the designed value.

Underground Test Area Project Waste Management Plan (Rev. No. 2, April 2002)

International Nuclear Information System (INIS)

IT Corporation, Las Vegas

2002-01-01

The U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Operations Office (NNSA/NV) initiated the UGTA Project to characterize the risk posed to human health and the environment as a result of underground nuclear testing activities at the Nevada Test Site (NTS). The UGTA Project investigation sites have been grouped into Corrective Action Units (CAUs) in accordance with the most recent version of the Federal Facility Agreement and Consent Order. The primary UGTA objective is to gather data to characterize the groundwater aquifers beneath the NTS and adjacent lands. The investigations proposed under the UGTA program may involve the drilling and sampling of new wells; recompletion, monitoring, and sampling of existing wells; well development and hydrologic/ aquifer testing; geophysical surveys; and subsidence crater recharge evaluation. Those wastes generated as a result of these activities will be managed in accordance with existing federal and state regulations, DOE Orders, and NNSA/NV waste minimization and pollution prevention objectives. This Waste Management Plan provides a general framework for all Underground Test Area (UGTA) Project participants to follow for the characterization, storage/accumulation, treatment, and disposal of wastes generated by UGTA Project activities. The objective of this waste management plan is to provide guidelines to minimize waste generation and to properly manage wastes that are produced. Attachment 1 to this plan is the Fluid Management Plan and details specific strategies for management of fluids produced under UGTA operations

Test plan for K Basin Sludge Canister and Floor Sampling Device

International Nuclear Information System (INIS)

Meling, T.A.

1995-01-01

This document provides the test plan and procedure forms for conducting the functional and operational acceptance testing of the K Basin Sludge Canister and Floor Sampling Device(s). These samplers samples sludge off the floor of the 100K Basins and out of 100K fuel storage canisters

Growth plan for an inspirational test-bed of smart textile services

NARCIS (Netherlands)

Wensveen, S.A.G.; Tomico, O.; Bhomer, ten M.; Kuusk, K.

2015-01-01

In this pictorial we visualize the growth plan for an inspirational test-bed of smart textile product service systems. The goal of the test-bed is to inspire and inform the Dutch creative industries of textile, interaction and service design to combine their strengths and share opportunities. The

Full-scale aicraft tire pressure tests

OpenAIRE

FABRE, C; BALAY, Jean Maurice; LERAT, P; MAZARS, A

2009-01-01

This paper describes an outdoor full-scale test planned to improve experimental and theoretical knowledge related to the effects of aircraft internal tire inflation pressure on the behavior and damage of flexible pavement. Since modern aircraft can have tire pressures greater than 15 bar, the tests focus on pressures from 15 to 17.5 bar. The experimental pavement located on the Toulouse-Blagnac airport in France will include up to seven al different test sections, representative of current ai...

Underground Test Area Quality Assurance Project Plan Nevada National Security Site, Nevada, Revision 0

Energy Technology Data Exchange (ETDEWEB)

Irene Farnham

2011-05-01

This Quality Assurance Project Plan (QAPP) provides the overall quality assurance (QA) program requirements and general quality practices to be applied to the U.S. Department of Energy (DOE), National Nuclear Security Administration Nevada Site Office (NNSA/NSO) Underground Test Area (UGTA) Sub-Project (hereafter the Sub-Project) activities. The requirements in this QAPP are consistent with DOE Order 414.1C, Quality Assurance (DOE, 2005); U.S. Environmental Protection Agency (EPA) Guidance for Quality Assurance Project Plans for Modeling (EPA, 2002); and EPA Guidance on the Development, Evaluation, and Application of Environmental Models (EPA, 2009). The QAPP Revision 0 supersedes DOE--341, Underground Test Area Quality Assurance Project Plan, Nevada Test Site, Nevada, Revision 4.

EBR-2 [Experimental Breeder Reactor-2] test programs

International Nuclear Information System (INIS)

Sackett, J.I.; Lehto, W.K.; Lindsay, R.W.; Planchon, H.P.; Lambert, J.D.B.; Hill, D.J.

1990-01-01

The Experimental Breeder Reactor-2 (EBR-2) is a sodium cooled power reactor supplying about 20 MWe to the Idaho National Engineering Laboratory (INEL) grid and, in addition, is the key component in the development of the Integral Fast Reactor (IFR). EBR-2's testing capability is extensive and has seen four major phases: (1) demonstration of LMFBR power plant feasibility, (2) irradiation testing for fuel and material development, (3) testing the off-normal performance of fuel and plant systems and (4) operation as the IFR prototype, developing and demonstrating the IFR technology associated with fuel and plant design. Specific programs being carried out in support of the IFR include advanced fuels and materials development, advanced control system development, plant diagnostics development and component testing. This paper discusses EBR-2 as the IFR prototype and the associated testing programs. 29 refs

Minnesota urban partnership agreement national evaluation : content analysis test plan.

Science.gov (United States)

2009-11-17

This report presents the content analysis test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employing ...

Minnesota urban partnership agreement national evaluation : safety data test plan.

Science.gov (United States)

2009-11-17

This report provides the safety data test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employing strat...

Minnesota urban partnership agreement national evaluation : exogenous factors test plan.

Science.gov (United States)

2009-11-17

This report presents the exogenous factors test plan for the national evaluation of the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reduc...

Micro-compression testing: A critical discussion of experimental constraints

International Nuclear Information System (INIS)

Kiener, D.; Motz, C.; Dehm, G.

2009-01-01

Micro-compression testing is a promising technique for determining mechanical properties at small length scales since it has several benefits over nanoindentation. However, as for all new techniques, experimental constraints influencing the results of such a micro-mechanical test must be considered. Here we investigate constraints imposed by the sample geometry, the pile-up of dislocations at the sample top and base, and the lateral stiffness of the testing setup. Using a focused ion beam milling setup, single crystal Cu specimens with different geometries and crystal orientations were fabricated. Tapered samples served to investigate the influence of strain gradients, while stiff sample top coatings and undeformable substrates depict the influence of dislocation pile-ups at these interfaces. The lateral system stiffness was reduced by placing specimens on top of needles. Samples were loaded using an in situ indenter in a scanning electron microscope in load controlled or displacement controlled mode. The observed differences in the mechanical response with respect to the experimental imposed constraints are discussed and lead to the conclusion that controlling the lateral system stiffness is the most important point

Experimental Modal Test of the Laboratory Model of Steel Truss Structure

Directory of Open Access Journals (Sweden)

Kortiš Ján

2016-12-01

Full Text Available The experimental modal analysis is often used to validate the accuracy of dynamic numerical models. It is also a good tool to obtain valuable information about current condition of the structures that could help to determine residual lifetime. The quality of modal testing results is highly dependent on the proper estimation of the natural frequencies from the frequency response function. This article presents the experimental modal test of the laboratory steel structure in which the natural frequencies and mode shapes are determined.

Nevada Test Site Resource Management Plan

Energy Technology Data Exchange (ETDEWEB)

NONE

1998-12-01

The Nevada Test Site (NTS) Resource Management Plan (RMP) describes the NTS Stewardship Mission and how its accomplishment will preserve the resources of the ecoregion while accomplishing the objectives of the mission. The NTS Stewardship Mission is to manage the land and facilities at the NTS as a unique and valuable national resource. The RMP has defined goals for twelve resource areas based on the principles of ecosystem management. These goals were established using an interdisciplinary team of DOE/NV resource specialists with input from surrounding land managers, private parties, and representatives of Native American governments. The overall goal of the RMP is to facilitate improved NTS land use management decisions within the Great Basin and Mojave Desert ecoregions.

Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1998

International Nuclear Information System (INIS)

Haagenstad, T.

1999-01-01

This Mitigation Action Plan Annual Report (MAPAR) has been prepared as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP) to protect workers, soils, water, and biotic and cultural resources in and around the facility

Dual Axis Radiographic Hydrodynamic Test Facility mitigation action plan. Annual report for 1998

Energy Technology Data Exchange (ETDEWEB)

Haagenstad, T.

1999-01-15

This Mitigation Action Plan Annual Report (MAPAR) has been prepared as part of implementing the Dual Axis Radiographic Hydrodynamic Test Facility (DARHT) Mitigation Action Plan (MAP) to protect workers, soils, water, and biotic and cultural resources in and around the facility.

MOTIVATION AND PERFORMANCE IN PHYSICAL EDUCATION: AN EXPERIMENTAL TEST

Directory of Open Access Journals (Sweden)

Juan A. Moreno

2010-03-01

Full Text Available The purpose of this study was to analyse, experimentally, the relationships between motivation and performance in a lateral movement test in physical education. The study group consisted of 363 students (227 boys and 136 girls, aged between 12 and 16, who were randomly divided into three groups: an experimental group in which an incremental ability belief was induced, another experimental group in which an entity ability belief was induced, and a control group where there was no intervention. Measurements were made of situational intrinsic motivation, perceived competence in executing the task and performance. The results revealed that the incremental group reported higher scores on the situational intrinsic motivation scale. The entity group demonstrated better performance in the first test attempt than the incremental group but, in the second attempt, the performance was similar in the different groups. Perhaps the initial differences in performance disappeared because the incremental group counted on improving in the second attempt. These results are discussed in relation to the intensity with which the teacher conveys information relating to incremental ability belief of the pupil to increase intrinsic motivation and performance

A test sheet generating algorithm based on intelligent genetic algorithm and hierarchical planning

Science.gov (United States)

Gu, Peipei; Niu, Zhendong; Chen, Xuting; Chen, Wei

2013-03-01

In recent years, computer-based testing has become an effective method to evaluate students' overall learning progress so that appropriate guiding strategies can be recommended. Research has been done to develop intelligent test assembling systems which can automatically generate test sheets based on given parameters of test items. A good multisubject test sheet depends on not only the quality of the test items but also the construction of the sheet. Effective and efficient construction of test sheets according to multiple subjects and criteria is a challenging problem. In this paper, a multi-subject test sheet generation problem is formulated and a test sheet generating approach based on intelligent genetic algorithm and hierarchical planning (GAHP) is proposed to tackle this problem. The proposed approach utilizes hierarchical planning to simplify the multi-subject testing problem and adopts genetic algorithm to process the layered criteria, enabling the construction of good test sheets according to multiple test item requirements. Experiments are conducted and the results show that the proposed approach is capable of effectively generating multi-subject test sheets that meet specified requirements and achieve good performance.

Test plan for Enraf Series 854 level gauge testing in Tank 241-S-106

International Nuclear Information System (INIS)

Barnes, G.A.

1994-01-01

An Enraf Series 854 level gauge was installed on Tank 241-S-106 (S-106) during the first week of June 1994. On August 11, 1994, the gauge's measuring wire broke. An investigation has been started to determine how the wire broke. This test plan identifies a qualification test that is part of this investigation. This test will also provide evidence as to the location and extent of potential corrosion on the measuring wire due to tank environment. The results from this testing will provide data for better material selections. This test will involve placing the existing Enraf Series 854 level gauge back into service with the same type of measuring wire (316 stainless steel) that originally broke on August 11, 1994. The gauge will be operated for 14 days. At the end of the 14-day test, the wire shall be sent to Pacific Northwest Laboratory (PNL) for analysis

Test particle calculations for the Texas experimental tokamak with resonant magnetic fields

International Nuclear Information System (INIS)

Wootton, A.J.; McCool, S.C.; Zheng, S.

1991-01-01

This paper presents a simple test particle model that attempts to describe particle motion in the presence of intrinsic electrostatic fluctuations in a prescribed tokamak magnetic field. In particular, magnetic field configurations that include externally produced magnetic islands and stochastic regions are considered. The resulting test particle transport is compared with the predictions of analytic models and with the experimentally measured electron heat and particle transport on the Texas Experimental Tokamak (TEXT). Agreement between the test particle results and applicable analytic theories is found. However, there is only partial agreement with the experimental results, and possible reasons for the discrepancies are explored. Good agreement is found between predicted and measured spatially asymmetric particle distributions. The particle collection efficiency of an apertured limiter inside a magnetic island (an intra-island pump limiter) is discussed

J-PARC Transmutation Experimental Facility Programme

International Nuclear Information System (INIS)

Sasa, T.; Takei, H.; Saito, S.; Obayashi, H.; Nishihara, K.; Sugawara, T.; Iwamoto, H.; Yamaguchi, K.; Tsujimoto, K.; Oigawa, H.

2015-01-01

Since the Fukushima accident, nuclear transmutation is considered as an option for waste management. Japan Atomic Energy Agency proposes the transmutation of minor actinides (MA) in accelerator-driven system (ADS) using lead-bismuth eutectic alloy (LBE) as a spallation target and a coolant of subcritical core. To obtain the data required for ADS design, we plan the building of a transmutation experimental facility (TEF) is planned within the J-PARC project. TEF consists of an ADS target test facility (TEF-T), which will be installed 400 MeV-250 kW LBE spallation target for material irradiations, and a transmutation physics experimental facility (TEF-P), which set up a fast critical/subcritical assembly driven by low power proton beam with MA fuel to study ADS neutronics. At TEF-T, various research plans to use emitted neutrons from LBE target are discussed. The paper summarises a road-map to establish the ADS transmuter and latest design activities for TEF construction. (authors)

Experimental system description for air-water CCFL tests of the 161-rod FLECHT-SEASET test vessel upper plenum

International Nuclear Information System (INIS)

Fogdall, S.P.; Anderson, J.L.

1983-01-01

A series of countercurrent flow limiting (CCFL) experiments has been performed by EG and G Idaho, Inc. in the Steam-Air-Water (SAW) test facility at the Idaho National Engineering Laboratory on behalf of the US Nuclear Regulatory Commission (NRC). Tests were performed in a mockup of the vessel for the 161-Rod Systems Effects Test (SET) facility of the FLECHT-SEASET program, conducted by the Westinghouse Electric Corporation. Westinghouse and the NRC will use the test results to provide a CCFL correlation to predict the flooding behavior in the upper plenum of the SET vessel. This paper presents a description of the experimental system and the test conduct, including data validation and uncertainty analysis. The test objectives centered on experimentally obtaining coefficients in the Wallis correlation for flooding with the specific vessel geometry. The test conditions and vessel configuration are described and the design of the test loop, instrumentation, and data acquisition are discussed. The establishment of a test point and the resultant data are described

Full-scale aircraft tire pressure tests

OpenAIRE

FABRE, C; BALAY, Jean Maurice; LERAT, P; MAZARS, A

2009-01-01

This paper describes an outdoor full-scale test planned to improve experimental and theoretical knowledge related to the effects of aircraft internal tire inflation pressure on the behavior and damage of flexible pavement. Since modern aircraft can have tire pressures greater than 15 bar, the tests will focus on pressures from 15 bar to 17.5 bar. The experimental pavement located on the Toulouse-Blagnac airport in France will include up to seven al different test sections, representative of c...

Optimal Constant-Stress Accelerated Degradation Test Plans Using Nonlinear Generalized Wiener Process

Directory of Open Access Journals (Sweden)

Zhen Chen

2016-01-01

Full Text Available Accelerated degradation test (ADT has been widely used to assess highly reliable products’ lifetime. To conduct an ADT, an appropriate degradation model and test plan should be determined in advance. Although many historical studies have proposed quite a few models, there is still room for improvement. Hence we propose a Nonlinear Generalized Wiener Process (NGWP model with consideration of the effects of stress level, product-to-product variability, and measurement errors for a higher estimation accuracy and a wider range of use. Then under the constraints of sample size, test duration, and test cost, the plans of constant-stress ADT (CSADT with multiple stress levels based on the NGWP are designed by minimizing the asymptotic variance of the reliability estimation of the products under normal operation conditions. An optimization algorithm is developed to determine the optimal stress levels, the number of units allocated to each level, inspection frequency, and measurement times simultaneously. In addition, a comparison based on degradation data of LEDs is made to show better goodness-of-fit of the NGWP than that of other models. Finally, optimal two-level and three-level CSADT plans under various constraints and a detailed sensitivity analysis are demonstrated through examples in this paper.

Hanford Permanent Isolation Barrier Program: Asphalt technology test plan

Energy Technology Data Exchange (ETDEWEB)

Freeman, H.D.; Romine, R.A.

1994-05-01

The Hanford Permanent Isolation Barriers use engineered layers of natural materials to create an integrated structure with backup protective features. The objective of current designs is to develop a maintenance-free permanent barrier that isolates wastes for a minimum of 1000 years by limiting water drainage to near-zero amounts. Asphalt is being used as an impermeable water diversion layer to provide a redundant layer within the overall barrier design. Data on asphalt barrier properties in a buried environment are not available for the required 100-year time frame. The purpose of this test plan is to outline the activities planned to obtain data with which to estimate performance of the asphalt layers.

Hanford Permanent Isolation Barrier Program: Asphalt technology test plan

International Nuclear Information System (INIS)

Freeman, H.D.; Romine, R.A.

1994-05-01

The Hanford Permanent Isolation Barriers use engineered layers of natural materials to create an integrated structure with backup protective features. The objective of current designs is to develop a maintenance-free permanent barrier that isolates wastes for a minimum of 1000 years by limiting water drainage to near-zero amounts. Asphalt is being used as an impermeable water diversion layer to provide a redundant layer within the overall barrier design. Data on asphalt barrier properties in a buried environment are not available for the required 100-year time frame. The purpose of this test plan is to outline the activities planned to obtain data with which to estimate performance of the asphalt layers

CWTC Business Plan

DEFF Research Database (Denmark)

Jensen, Peter Hjuler; Hillestrøm, Adam; Markou, Helen

level improving the competitive advantage of that industry. The CWTC will in itself operate its activities, including access to test and experimental facilities, on a semi commercial basis. The business model for the CWTC presented is based on revenues coming from component manufacturers as well......This report presents the Business Plan for the establishment of the Wind Turbine Component Centre (CWTC) to meet the objectives of performing theoretical research and experimental testing. The core idea of a CWTC is to support the Danish wind energy industry and research activities at the component...... suppliers to the Danish wind turbine industry and also the Danish research establishments. The presented organizational structure reflects that there are certain functions that are separated from the operations and it also reflects that scientific staffing are hired in on a project basis. Machine operators...

Proposed experimental test of an alternative electrodynamic theory of superconductors

Energy Technology Data Exchange (ETDEWEB)

Hirsch, J.E., E-mail: jhirsch@ucsd.edu

2015-01-15

Highlights: • A new experimental test of electric screening in superconductors is proposed. • The electric screening length is predicted to be much larger than in normal metals. • The reason this was not seen in earlier experiments is explained. • This is not predicted by the conventional BCS theory of superconductivity. - Abstract: An alternative form of London’s electrodynamic theory of superconductors predicts that the electrostatic screening length is the same as the magnetic penetration depth. We argue that experiments performed to date do not rule out this alternative formulation and propose an experiment to test it. Experimental evidence in its favor would have fundamental implications for the understanding of superconductivity.

A nuclear power plant certification test plan and checklist

International Nuclear Information System (INIS)

Halverson, S.M.

1989-01-01

Regulations within the nuclear industry are requiring that all reference plant simulators be certified prior to or during 1991. A certification test plan is essential to ensure that this goal is met. A description of each step in the certification process is provided in this paper, along with a checklist to help ensure completion of each item

Acceptance Test Plan for Fourth-Generation Corrosion Monitoring Cabinet

International Nuclear Information System (INIS)

NORMAN, E.C.

2000-01-01

This Acceptance Test Plan (ATP) will document the satisfactory operation of the third-generation corrosion monitoring cabinet (Hiline Engineering Part No.0004-CHM-072-C01). This ATP will be performed by the manufacturer of the cabinet prior to delivery to the site. The objective of this procedure is to demonstrate and document the acceptance of the corrosion monitoring cabinet. The test will consist of a continuity test of the cabinet wiring from the end of cable to be connected to corrosion probe, through the appropriate intrinsic safety barriers and out to the 15 pin D-shell connectors to be connected to the corrosion monitoring instrument. Additional testing will be performed using a constant current and voltage source provided by the corrosion monitoring hardware manufacturer to verify proper operation of corrosion monitoring instrumentation

Abbreviated sampling and analysis plan for planning decontamination and decommissioning at Test Reactor Area (TRA) facilities

International Nuclear Information System (INIS)

1994-10-01

The objective is to sample and analyze for the presence of gamma emitting isotopes and hazardous constituents within certain areas of the Test Reactor Area (TRA), prior to D and D activities. The TRA is composed of three major reactor facilities and three smaller reactors built in support of programs studying the performance of reactor materials and components under high neutron flux conditions. The Materials Testing Reactor (MTR) and Engineering Test Reactor (ETR) facilities are currently pending D/D. Work consists of pre-D and D sampling of designated TRA (primarily ETR) process areas. This report addresses only a limited subset of the samples which will eventually be required to characterize MTR and ETR and plan their D and D. Sampling which is addressed in this document is intended to support planned D and D work which is funded at the present time. Biased samples, based on process knowledge and plant configuration, are to be performed. The multiple process areas which may be potentially sampled will be initially characterized by obtaining data for upstream source areas which, based on facility configuration, would affect downstream and as yet unsampled, process areas. Sampling and analysis will be conducted to determine the level of gamma emitting isotopes and hazardous constituents present in designated areas within buildings TRA-612, 642, 643, 644, 645, 647, 648, 663; and in the soils surrounding Facility TRA-611. These data will be used to plan the D and D and help determine disposition of material by D and D personnel. Both MTR and ETR facilities will eventually be decommissioned by total dismantlement so that the area can be restored to its original condition

Time reversal violation in radiative beta decay: experimental plans

Science.gov (United States)

Behr, J. A.; McNeil, J.; Anholm, M.; Gorelov, A.; Melconian, D.; Ashery, D.

2017-01-01

Some explanations for the excess of matter over antimatter in the universe involve sources of time reversal violation (TRV) in addition to the one known in the standard model of particle physics. We plan to search for TRV in a correlation between the momenta of the beta, neutrino, and the radiative gamma sometimes emitted in nuclear beta decay. Correlations involving three (out of four) momenta are sensitive at lowest order to different TRV physics than observables involving spin, such as electric dipole moments and spin-polarized beta decay correlations. Such experiments have been done in radiative kaon decay, but not in systems involving the lightest generation of quarks. An explicit low-energy physics model being tested produces TRV effects in the Fermi beta decay of the neutron, tritium, or some positron-decaying isotopes. We will present plans to measure the TRV asymmetry in radiative beta decay of laser-trapped 38mK at better than 0.01 sensitivity, including suppression of background from positron annihilation. Supported by NSERC, D.O.E., Israel Science Foundation. TRIUMF receives federal funding via a contribution agreement with the National Research Council of Canada.

Detailed leak detection test plan and schedule for Oak Ridge National Laboratory liquid low-level waste active tanks

International Nuclear Information System (INIS)

1995-01-01

This document provides a plan and schedule for leak testing a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. It is a concise version of a more general leak testing plan that was prepared in response to the requirements of the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). This plan includes a schedule for the initial reporting of the leak test results from the various tanks that will be tested. The FFA distinguishes four categories of tank and pipeline systems: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems; there are 14 such tanks addressed in this plan, plus one tank (W-12) that has been temporarily returned to service based on EPA and TDEC concurrence. A schedule for testing these tanks is also included. The plan and schedule also addresses an additional 15 Category B tanks have been demonstrated to meet secondary containment requirements. While these 15 tanks are addressed in this plan for the sake of completeness, they have been removed from the leak testing program based on the design demonstrations that show secondary containment. It is noted that the general plan included 42 tanks. Since that report was issued, 26 of those tanks have passed secondary containment design demonstrations and subsequently have been removed from this leak testing plan. In addition, one tank (LA-104) has been removed from service. Accordingly, this document addresses 15 of the LLLW tanks in the system; plans for testing the pipelines will be described in a separate document

Detailed leak detection test plan and schedule for Oak Ridge National Laboratory liquid low-level waste active tanks

Energy Technology Data Exchange (ETDEWEB)

NONE

1995-01-01

This document provides a plan and schedule for leak testing a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL), Oak Ridge, Tennessee. It is a concise version of a more general leak testing plan that was prepared in response to the requirements of the Federal Facility Agreement (FFA) for the Oak Ridge Reservation (ORR). This plan includes a schedule for the initial reporting of the leak test results from the various tanks that will be tested. The FFA distinguishes four categories of tank and pipeline systems: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems; there are 14 such tanks addressed in this plan, plus one tank (W-12) that has been temporarily returned to service based on EPA and TDEC concurrence. A schedule for testing these tanks is also included. The plan and schedule also addresses an additional 15 Category B tanks have been demonstrated to meet secondary containment requirements. While these 15 tanks are addressed in this plan for the sake of completeness, they have been removed from the leak testing program based on the design demonstrations that show secondary containment. It is noted that the general plan included 42 tanks. Since that report was issued, 26 of those tanks have passed secondary containment design demonstrations and subsequently have been removed from this leak testing plan. In addition, one tank (LA-104) has been removed from service. Accordingly, this document addresses 15 of the LLLW tanks in the system; plans for testing the pipelines will be described in a separate document.

Persistência do plano experimental em ensaios de avaliação de germoplasma elite de feijão Experimental plan persistence in elite genotypes evaluation for beans assays

Directory of Open Access Journals (Sweden)

Lindolfo Storck

2007-12-01

culture, during seven years (2000 to 2006. Fourteen competitive assays of elite genotype beans had been tested in Santa Maria, State of Rio Grande do Sul, Brazil - in two growing seasons (normal and off season crops, with different treat numbers (advanced lines and variety. The experiment was carried out in a randomized complete block design with three replications. For each assay, the mean, variation coefficient, intraclass correlation coefficient and heterogeneity index of the grain yield of beans were determined. Also the true differences between two means of treatments by Hatheway methods, using for different values of the heterogeneity index, repetition number had been estimated together with the plot size. The frequency of the heterogeneity index between 0.2 and 0.7 was 71%, evidencing that the experimental plan, on the basis of the results of previous experiments, has validity in 71% of the cases. It does not seem to have b predominance in function of the growing seasons - normal and late season crops, or of the type of experiment - VCU or variety, showing a good repeatability or persistence in elapsing of the years.

Operations plan for the Regional Seismic Test Network

International Nuclear Information System (INIS)

1981-01-01

The Regional Seismic Test Network program was established to provide a capability for detection of extremely sensitive earth movements. Seismic signals from both natural and man-made earth motions will be analyzed with the ultimate objective of accurately locating underground nuclear explosions. The Sandia National Laboratories, Albuquerque, has designed an unattended seismic station capable of recording seismic information received at the location of the seismometers installed as part of that specific station. A network of stations is required to increase the capability of determining the source of the seismic signal and the location of the source. Current plans are to establish a five-station seismic network in the United States and Canada. The Department of Energy, Nevada Operations Office, has been assigned the responsibility for deploying, installing, and operating these remote stations. This Operation Plan provides the basic information and tasking to accomplish this assignment

Plan for 3-D full-scale earthquake testing facility

International Nuclear Information System (INIS)

Ohtani, K.

2001-01-01

Based on the lessons learnt from the Great Hanshin-Awaji Earthquake, National Research Institute for Earth Science and Disaster Prevention plan to construct the 3-D Full-Scale Earthquake Testing Facility. This will be the world's largest and strongest shaking table facility. This paper describes the outline of the project for this facility. This facility will be completed in early 2005. (author)

Project Rio Blanco definition plan. Additional formation evaluation and production testing

International Nuclear Information System (INIS)

1975-09-01

Since the multiple Rio Blanco detonation three reentry wells have been drilled for test purposes: RB-E-01 (Emplacement Well); RB-AR-2 (Alternate Reentry Well); and RB-U-4 (Formation Evaluation Well). Additional testing in all these wells is now required to resolve some remaining technical questions. A plan describing the procedures, methods, responsibilities, and scheduling of the field operations is presented

Setup of a testing environment for mission planning in mining

NARCIS (Netherlands)

Groenen, J.P.J.; Steinbuch, M.

2013-01-01

Mission planning algorithms for surface mining applications are difficult to test as a result of the large scale tasks. To validate these algorithms, a scaled setup is created where the mining excavator is mimicked by an industrial robot. This report discusses the development of a software

Modeling and experimental testing activity of the Voltage Optimization Unit

DEFF Research Database (Denmark)

Zecchino, Antonio; Hu, Junjie; Marinelli, Mattia

In the EUDP project ‘Energy saving by voltage management’ two reports are provided by Technical University of Denmark (DTU) covering the simulation studies and experimental work. The first report presented the simulation results regarding the technical evaluation of on-load tap changers in solving...... and distributed power systems, located at DTU Risø campus. The experimental test validates the control performance of the OLTC transformer and the test indicates that, using remote measurement, the voltage of the system can be kept in a safe operational band. However, the remote measurement implies additional...... cost investments of to the system operator, thus a proactive tap algorithm is developed and tested in this project, relying on local measurements. In addition, we also compared the experimental result with the one simulated in the DigSilent PowerFactory software environment (the software used...

Test plan for Enraf Series 854 level gauge wire testing

International Nuclear Information System (INIS)

Barnes, G.A.

1994-01-01

An Enraf Series 854 level gauge was installed on tank 241-S-106 during the first week of June 1994. On August 11, 1994, the gauge's stainless steel measuring wire broke. After examination and laboratory analysis, it was determined that the wire broke due to severe chloride ion corrosion. It is suspected that the chloride ion contamination came from the radiation induced breakdown of the polyvinyl chloride (PVC) riser liner. It is well documented that the breakdown of PVC due to radiation produces chloride containing compounds. This document provides a qualification test plan to remove and have analyzed the wire in all of the Enraf Series 854 that have been installed to date. These tests will confirm the presence or absence of chloride ions in the PVC liners and/or on the Enraf measuring wires installed in the tanks. This test will involve removing the 316 stainless steel wire drums from all of the existing Enraf Series 854 level gauges that have been installed. New 316 stainless steel wire drums shall be installed into the gauges and the gauges will be placed back into service. The wire that is removed from the gauges shall be sent to the 222-S Lab or the Pacific Northwest Laboratory (PNL) for analysis. Additional wire replacements will occur at intervals as determined necessary by the results of the laboratory analyses

Selenide isotope generator for the Galileo Mission: safety test plan

International Nuclear Information System (INIS)

1979-01-01

The intent of this safety test plan is to outline particular kinds of safety tests designed to produce information which would be useful in the safety analysis process. The program deals primarily with the response of the RTG to accident environments; accordingly two criteria were established: (1) safety tests should be performed for environments which are the most critical in terms of risk contribution; and (2) tests should be formulated to determine failure conditions for critical heat source components rather than observe heat source response in reference accident environments. To satisfy criterion 1. results of a recent safety study were used to rank various accidents in terms of expected source terms. Six kinds of tests were then proposed which would provide information meeting the second criterion

EXPERIMENTAL TESTING OF DRAW-BEAD RESTRAINING FORCE IN SHEET METAL FORMING

Institute of Scientific and Technical Information of China (English)

J.H. Yang; J. Chen; D.N. He; X. Y. Ruan

2003-01-01

Due to complexities of draw-bead restraining force calculated according to theory anddepending on sheet metal forming properties experiment testing system, a simplifiedmethod to calculate draw-bead restraining force is put forward by experimental methodin cup-shaped drawing process. The experimental results were compared with numer-ical results and proved agreement. It shows the method is effective.

Experimental test campaign on an ITER divertor mock-up

Energy Technology Data Exchange (ETDEWEB)

Dell' Orco, G. E-mail: giovanni.dellorco@brasimone.enea.it; Malavasi, A.; Merola, M.; Polazzi, G.; Simoncini, M.; Zito, D

2002-11-01

In 1998, in the frame of the European R and D on ITER high heat flux components, the fabrication of a full scale ITER Divertor Outboard mock-up was launched. It comprised a Cassette Body (CB), designed with some mechanical and hydraulic simplifications with respect to the reference body and its actively cooled Dummy Armour Prototype (DAP). This DAP consists of a Vertical Target (VT), a Wing (WI) and a Dump Target (DT), manufactured by European industries, which are integrated to the Gas Box Liner (GBL) supplied by the Russian Federation ITER Home Team. In 1999, in parallel with the manufacturing activity, the ITER European Home Team decided to assign to ENEA a Task for checking the component integration and performing the thermal-hydraulic and thermal mechanical testing of the DAP and CB. In 1999-2000, ENEA performed the experimental campaign at Brasimone Labs. The present work presents the experimental results of the component integration and the thermal-hydraulic and thermo-mechanical fatigue tests.

Experimental test campaign on an ITER divertor mock-up

International Nuclear Information System (INIS)

Dell'Orco, G.; Malavasi, A.; Merola, M.; Polazzi, G.; Simoncini, M.; Zito, D.

2002-01-01

In 1998, in the frame of the European R and D on ITER high heat flux components, the fabrication of a full scale ITER Divertor Outboard mock-up was launched. It comprised a Cassette Body (CB), designed with some mechanical and hydraulic simplifications with respect to the reference body and its actively cooled Dummy Armour Prototype (DAP). This DAP consists of a Vertical Target (VT), a Wing (WI) and a Dump Target (DT), manufactured by European industries, which are integrated to the Gas Box Liner (GBL) supplied by the Russian Federation ITER Home Team. In 1999, in parallel with the manufacturing activity, the ITER European Home Team decided to assign to ENEA a Task for checking the component integration and performing the thermal-hydraulic and thermal mechanical testing of the DAP and CB. In 1999-2000, ENEA performed the experimental campaign at Brasimone Labs. The present work presents the experimental results of the component integration and the thermal-hydraulic and thermo-mechanical fatigue tests

Experimental Issues in Testing a Semiactive Technique to Control Earthquake Induced Vibration

Directory of Open Access Journals (Sweden)

Nicola Caterino

2014-01-01

Full Text Available This work focuses on the issues to deal with when approaching experimental testing of structures equipped with semiactive control (SA systems. It starts from practical experience authors gained in a recent wide campaign on a large scale steel frame structure provided with a control system based on magnetorheological dampers. The latter are special devices able to achieve a wide range of physical behaviours using low-power electrical currents. Experimental activities involving the use of controllable devices require special attention in solving specific aspects that characterize each of the three phases of the SA control loop: acquisition, processing, and command. Most of them are uncommon to any other type of structural testing. This paper emphasizes the importance of the experimental assessment of SA systems and shows how many problematic issues likely to happen in real applications are also present when testing these systems experimentally. This paper highlights several problematic aspects and illustrates how they can be addressed in order to achieve a more realistic evaluation of the effectiveness of SA control solutions. Undesired and unavoidable effects like delays and control malfunction are also remarked. A discussion on the way to reduce their incidence is also offered.

Advantages of the experimental animal hollow organ mechanical testing system for the rat colon rupture pressure test.

Science.gov (United States)

Ji, Chengdong; Guo, Xuan; Li, Zhen; Qian, Shuwen; Zheng, Feng; Qin, Haiqing

2013-01-01

Many studies have been conducted on colorectal anastomotic leakage to reduce the incidence of anastomotic leakage. However, how to precisely determine if the bowel can withstand the pressure of a colorectal anastomosis experiment, which is called anastomotic bursting pressure, has not been determined. A task force developed the experimental animal hollow organ mechanical testing system to provide precise measurement of the maximum pressure that an anastomotic colon can withstand, and to compare it with the commonly used method such as the mercury and air bag pressure manometer in a rat colon rupture pressure test. Forty-five male Sprague-Dawley rats were randomly divided into the manual ball manometry (H) group, the tracing machine manometry pressure gauge head (MP) group, and the experimental animal hollow organ mechanical testing system (ME) group. The rats in each group were subjected to a cut colon rupture pressure test after injecting anesthesia in the tail vein. Colonic end-to-end anastomosis was performed, and the rats were rested for 1 week before anastomotic bursting pressure was determined by one of the three methods. No differences were observed between the normal colon rupture pressure and colonic anastomotic bursting pressure, which were determined using the three manometry methods. However, several advantages, such as reduction in errors, were identified in the ME group. Different types of manometry methods can be applied to the normal rat colon, but the colonic anastomotic bursting pressure test using the experimental animal hollow organ mechanical testing system is superior to traditional methods. Copyright © 2013 Surgical Associates Ltd. Published by Elsevier Ltd. All rights reserved.

Minnesota urban partnership agreement national evaluation : transit system data test plan.

Science.gov (United States)

2009-11-17

This report presents the test plan for collecting and analyzing transit system data for the Minnesota Urban Partnership Agreement (UPA) National Evaluation under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA...

San Francisco urban partnership agreement, national evaluation : content analysis test plan.

Science.gov (United States)

2011-06-01

This report presents the test plan for collecting and analyzing information on outreach activities, media coverage, : and reactions of the public, policy makers, and other groups to the UPA projects for the San Francisco Urban : Partnership Agreement...

Test plan: Air intake shaft performance test -- Addendum for obtaining cores in the Culebra for radionuclide retardation studies

International Nuclear Information System (INIS)

Gelbard, F.

1991-10-01

Core samples are needed for obtaining data on radionuclide retardation. The cores will be used to first determine local basic properties of Culebra rock such as permeability, structural integrity, fracture spacing, and fracture size. These quantities will then be used to design a laboratory experimental program to determine radionuclide retardation in a column flow apparatus using the cores obtained in this project. This addendum covers only the coring activities necessary to retrieve Culebra cores. The laboratory work will be documented in a separate test plan. It is anticipated that Culebra rock samples will be highly fractured, with a fracture spacing on the order of 2 to 3 inches To obtain representative core samples that are intact, horizontal cores about 6 inches in diameter and several feet long will be needed. These cores will provide a good indication of Culebra rock fracturing and provide several samples needed to conduct column flow experiments. If the rock is so fractured that only rubble is obtained, then the rubble will be used in the column experiments. In addition, as a byproduct of the coring operation, natural groundwater collected from the holes will be used to develop a synthetic brine for the laboratory experiments

Experimental Breeder Reactor II (EBR-II) Fuel-Performance Test Facility (FPTF)

International Nuclear Information System (INIS)

Pardini, J.A.; Brubaker, R.C.; Veith, D.J.; Giorgis, G.C.; Walker, D.E.; Seim, O.S.

1982-01-01

The Fuel-Performance Test Facility (FPTF) is the latest in a series of special EBR-II instrumented in-core test facilities. A flow control valve in the facility is programmed to vary the coolant flow, and thus the temperature, in an experimental-irradiation subassembly beneath it and coupled to it. In this way, thermal transients can be simulated in that subassembly without changing the temperatures in surrounding subassemblies. The FPTF also monitors sodium flow and temperature, and detects delayed neutrons in the sodium effluent from the experimental-irradiation subassembly beneath it. This facility also has an acoustical detector (high-temperature microphone) for detecting sodium boiling

Experimental and Computational Study of Ductile Fracture in Small Punch Tests

Directory of Open Access Journals (Sweden)

Betül Gülçimen Çakan

2017-10-01

Full Text Available A unified experimental-computational study on ductile fracture initiation and propagation during small punch testing is presented. Tests are carried out at room temperature with unnotched disks of different thicknesses where large-scale yielding prevails. In thinner specimens, the fracture occurs with severe necking under membrane tension, whereas for thicker ones a through thickness shearing mode prevails changing the crack orientation relative to the loading direction. Computational studies involve finite element simulations using a shear modified Gurson-Tvergaard-Needleman porous plasticity model with an integral-type nonlocal formulation. The predicted punch load-displacement curves and deformed profiles are in good agreement with the experimental results.

Experimental and Computational Study of Ductile Fracture in Small Punch Tests.

Science.gov (United States)

Gülçimen Çakan, Betül; Soyarslan, Celal; Bargmann, Swantje; Hähner, Peter

2017-10-17

A unified experimental-computational study on ductile fracture initiation and propagation during small punch testing is presented. Tests are carried out at room temperature with unnotched disks of different thicknesses where large-scale yielding prevails. In thinner specimens, the fracture occurs with severe necking under membrane tension, whereas for thicker ones a through thickness shearing mode prevails changing the crack orientation relative to the loading direction. Computational studies involve finite element simulations using a shear modified Gurson-Tvergaard-Needleman porous plasticity model with an integral-type nonlocal formulation. The predicted punch load-displacement curves and deformed profiles are in good agreement with the experimental results.

EXPERIMENTAL TESTING OF DRAW—BEAD RESTRAINING FORCE IN SHEET METAL FORMING

Institute of Scientific and Technical Information of China (English)

J.H.Yang; J.Chen; 等

2003-01-01

Due to complexities of draw-bead restraining force calculated according to theory and depending on sheet metal forming properties experiment testing system,a simplified method to calculate draw-bead restraining force is put forward by experimental method in cup-shaped drawing process.The experimental results were compared with numer-ical results and proved agreement.It shows the method is effective.

Leak testing plan for the Oak Ridge National Laboratory liquid low- level waste system (active tanks)

International Nuclear Information System (INIS)

Douglas, D.G.; Wise, R.F.; Starr, J.W.; Maresca, J.W. Jr.

1992-06-01

A leak testing plan for a portion of the Liquid Low-Level Waste (LLLW) system at the Oak Ridge National Laboratory (ORNL) is provided in the two volumes that form this document. This plan was prepared in response to the requirements of the Federal Facilities Agreement (FFA) between the US Department of Energy and two other agencies, the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC). The effective date of this agreement was 1 January 1992. The LLLW system is an interconnected complex of tanks and pipelines. The FFA distinguishes four different categories of tank and pipeline systems within this complex: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA's specific requirements for leak testing of the Category C systems is addressed in this plan. The plan also addresses leak testing of the Category B portions of the LLLW system. Leak testing of the Category B components was brought into the plan to supplement the secondary containment design demonstration effort that is under way for these components

The 3rd irradiation test plan of DUPIC fuel

Energy Technology Data Exchange (ETDEWEB)

Yang, Myung Seung; Song, K. C.; Park, J. H. and others

2001-05-01

The objective of the 3rd irradiation test of DUPIC fuel at the HANARO is to estimate the in-core behaviour of a DUPIC pellet that is irradiated up to more than average burnup of CANDU fuel. The irradiation of DUPIC fuel is planned to start at May 21, 2001, and will be continued at least for 8 months. The burnup of DUPIC fuel through this irradiation test is thought to be more than 7,000 MWd/tHE. The DUPIC irradiation rig instrumented with three SPN detectors will be used to accumulate the experience for the instrumented irradiation and to estimate the burnup of irradiated DUPIC fuel more accurately. Under normal operating condition, the maximum linear power of DUPIC fuel was estimated as 55.06 kW/m, and the centerline temperature of a pellet was calculated as 2510 deg C. In order to assess the integrity of DUPIC fuel under the accident condition postulated at the HANARO, safety analyses on the locked rotor and reactivity insertion accidents were carried out. The maximum centerline temperature of DUPIC fuel was estimated 2590 deg C and 2094 deg C for each accident, respectively. From the results of the safety analysis, the integrity of DUPIC fuel during the HANARO irradiation test will be secured. The irradiated DUPIC fuel will be transported to the IMEF. The post-irradiation examinations are planned to be performed at the PIEF and IMEF.

Minnesota urban partnership agreement national evaluation : traffic system data test plan.

Science.gov (United States)

2009-11-17

This report presents the traffic system data test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by employi...

Minnesota urban partnership agreement national evaluation : cost benefit analysis test plan.

Science.gov (United States)

2009-11-17

This report presents the cost benefit analysis test plan for the Minnesota Urban Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. The Minnesota UPA projects focus on reducing congestion by emplo...

San Francisco urban partnership agreement, national evaluation : exogenous factors test plan.

Science.gov (United States)

2011-06-01

This report presents the test plan for collecting and analyzing exogenous factors data for the San Francisco Urban : Partnership Agreement (UPA) under the United States Department of Transportation (U.S. DOT) UPA Program. : The San Francisco UPA proj...

Physical Education Experimental Program to Test the Effect on Perceived Competence

Directory of Open Access Journals (Sweden)

Edin Brankovic

2017-06-01

Full Text Available The first purpose of this study was to test effect of multidisciplinary and holistic experimental program (EP in physical education program effect on the soul need perceived competence. The second purpose of this study was to analyse the relationship between attitudes of perceived competence in the experimental group before and after the application of program, mostly due the theoretical reason that perceived competence is predictor of Flow. The data was collected from 74 students of the 8th grade of elementary schools randomly divided in two groups (experimental: 53; control: 21. The system of variables consisted of perceived competence scale items. The t-test analysis was applied to test perceived competence attitudes before and after the EP. The experimental group attitudes of perceived competence after the EP were significantly more positive than before participation in it, while control group attitudes of perceived competence decreased after participation in the regular school program. The current findings support the authors’ hypothesis that the holistic program has significant effect on the soul need perceived competence which is closest predictor of Flow. This study applied multidisciplinary EP which was designed on growth-mind set practices and sparks findings–both connected to flow experience and intrinsic motivation–to suggest future comprehensive program that could be potentially used as a regular tool for achieving both, Flow and intrinsic motivation. Findings with certainty provide a basis for future necessary qualitative research of the program effects on the intrinsic motivation.

Experimental Results of Integrated Refrigeration and Storage System Testing

Science.gov (United States)

Notardonato, W. U.; Johnson, W. L.; Jumper, K.

2009-01-01

Launch operations engineers at the Kennedy Space Center have identified an Integrated Refrigeration and Storage system as a promising technology to reduce launch costs and enable advanced cryogenic operations. This system uses a close cycle Brayton refrigerator to remove energy from the stored cryogenic propellant. This allows for the potential of a zero loss storage and transfer system, as well and control of the state of the propellant through densification or re-liquefaction. However, the behavior of the fluid in this type of system is different than typical cryogenic behavior, and there will be a learning curve associated with its use. A 400 liter research cryostat has been designed, fabricated and delivered to KSC to test the thermo fluid behavior of liquid oxygen as energy is removed from the cryogen by a simulated DC cycle cryocooler. Results of the initial testing phase focusing on heat exchanger characterization and zero loss storage operations using liquid oxygen are presented in this paper. Future plans for testing of oxygen densification tests and oxygen liquefaction tests will also be discussed. KEYWORDS: Liquid Oxygen, Refrigeration, Storage

Field testing plan for unsaturated zone monitoring and field studies

International Nuclear Information System (INIS)

Young, M.H.; Wierenga, P.J.; Warrick, A.W.

1996-10-01

The University of Arizona, in cooperation with the Bureau of Economic Geology at The University of Texas at Austin, and Stephens and Associates in Albuquerque, New Mexico has developed a field testing plan for evaluating subsurface monitoring systems. The U.S. Nuclear Regulatory Commission has requested development of these testing plans for low-level radioactive waste disposal sites (LLW) and for monitoring at decommissioned facilities designated under the open-quotes Site Decommissioning Management Planclose quotes (SDMP). The tests are conducted on a 50 m by 50 m plot on the University of Arizona's Maricopa Agricultural Center. Within the 50 m by 50 m plot one finds: (1) an instrumented buried trench, (2) monitoring islands similar to those proposed for the Ward Valley, California LLW Facility, (3) deep borehole monitoring sites, (4) gaseous transport monitoring, and (5) locations for testing non-invasive geophysical measurement techniques. The various subplot areas are instrumented with commercially available instruments such as neutron probes, time domain reflectometry probes, tensiometers, psychrometers, heat dissipation sensors, thermocouples, solution samplers, and cross-hole geophysics electrodes. Measurement depths vary from ground surface to 15 m. The data from the controlled flow and transport experiments, conducted over the plot, will be used to develop an integrated approach to long-term monitoring of the vadose zone at waste disposal sites. The data will also be used to test field-scale flow and transport models. This report describes in detail the design of the experiment and the methodology proposed for evaluating the data

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

Energy Technology Data Exchange (ETDEWEB)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available.

Test program element II blanket and shield thermal-hydraulic and thermomechanical testing, experimental facility survey

International Nuclear Information System (INIS)

Ware, A.G.; Longhurst, G.R.

1981-12-01

This report presents results of a survey conducted by EG and G Idaho to determine facilities available to conduct thermal-hydraulic and thermomechanical testing for the Department of Energy Office of Fusion Energy First Wall/Blanket/Shield Engineering Test Program. In response to EG and G queries, twelve organizations (in addition to EG and G and General Atomic) expressed interest in providing experimental facilities. A variety of methods of supplying heat is available

Final closure plan for the high-explosives open burn treatment facility at Lawrence Livermore National Laboratory Experimental Test Site 300

Energy Technology Data Exchange (ETDEWEB)

Mathews, S.

1997-04-01

This document addresses the interim status closure of the HE Open Bum Treatment Facility, as detailed by Title 22, Division 4.5, Chapter 15, Article 7 of the Califonia Code of Regulations (CCR) and by Title 40, Code of Federal Regulations (CFR) Part 265, Subpart G, ``Closure and Post Closure.`` The Closure Plan (Chapter 1) and the Post- Closure Plan (Chapter 2) address the concept of long-term hazard elimination. The Closure Plan provides for capping and grading the HE Open Bum Treatment Facility and revegetating the immediate area in accordance with applicable requirements. The Closure Plan also reflects careful consideration of site location and topography, geologic and hydrologic factors, climate, cover characteristics, type and amount of wastes, and the potential for contaminant migration. The Post-Closure Plan is designed to allow LLNL to monitor the movement, if any, of pollutants from the treatment area. In addition, quarterly inspections will ensure that all surfaces of the closed facility, including the cover and diversion ditches, remain in good repair, thus precluding the potential for contaminant migration.

Acceptance Sampling Plans Based on Truncated Life Tests for Sushila Distribution

Directory of Open Access Journals (Sweden)

Amer Ibrahim Al-Omari

2018-03-01

Full Text Available An acceptance sampling plan problem based on truncated life tests when the lifetime following a Sushila distribution is considered in this paper. For various acceptance numbers, confidence levels and values of the ratio between fixed experiment time and particular mean lifetime, the minimum sample sizes required to ascertain a specified mean life were found. The operating characteristic function values of the suggested sampling plans and the producer’s risk are presented. Some tables are provided and the results are illustrated by an example of a real data set.

Experimental logistics plan in support of Extensive Separations for Hanford tank waste remediation systems

International Nuclear Information System (INIS)

Enderlin, W.I.; Swanson, J.L.; Carlson, C.D.; Hirschi, E.J.

1993-12-01

All proposed methods for remediating the radioactive and chemical waste stored in single- and double-shell tanks (SSTs and DSTs) at the Hanford Site require the separation of the waste mixtures in the tank into high-level and low-level fractions, the safe transport of this separated waste to appropriate immobilization facilities, and the long-term disposal of the immobilized waste forms. Extensive experimentation, especially in waste separations, will be required to develop the technologies and to produce the data that support the most effective and safe cleanup processes. As part of this effort, Pacific Northwest Laboratory (PNL) is developing this detailed experimental logistics plan to determine the logistical/resource requirements, and ultimately the critical paths, necessary to effectively and safely conduct the multitude of experiments within the Extensive Separations Development Program, which addresses the experimental needs of a concept that provides a high degree of separation for the high-level and low-level waste fractions. The logistics issues developed for this program are expected to be similar to those for other programs aimed at remediating and disposing of the wastes

Modeling and experimental tests of a copper thermosyphon

Directory of Open Access Journals (Sweden)

Paulo Henrique Dias dos Santos

2017-02-01

Full Text Available Electrical energy, solar energy, and/or direct combustion of a fuel are the most common thermal sources for home water heating. In recent years, the use of solar energy has become popular because it is a renewable and economic energy source. Among the solar collectors, those assisted by thermosyphons are more efficient; therefore, they can enhance the heat transfer to water. A thermosyphon is basically a sealed tube filled with a working fluid and, normally, it has three regions: the evaporator, the adiabatic section and the condenser. The great advantage of this device is that the thermal resistance to heat transfer between its regions is very small, and as a result, there is a small temperature difference. This article aims to model a thermosyphon by using correlations based on its operation limits. This modeling will be used as a design tool for compact solar collectors assisted by thermosyphons. Based on the results obtained with the mathematical modeling, one copper thermosyphon, with deionized water as the working fluid, was developed and experimentally tested. The tests were carried out for a heat load varying from 30 to 60W in a vertical position. The theoretical and experimental results were compared to verify the mathematical model.

An Experimental Test of the Effects of Gender Constancy on Sex Typing

Science.gov (United States)

Arthur, Andrea E.; Bigler, Rebecca S.; Ruble, Diane N.

2009-01-01

This study provides an experimental test of the hypothesis that level of gender constancy understanding affects children's sex typing. Preschool-age children (N = 62, mean age = 47 months) were randomly assigned to experimental lessons that taught that biological traits (including gender) are either fixed (pro-constancy condition) or mutable…

Test plan for evaluation of plasma melter technology for vitrification of high-sodium content low-level radioactive liquid wastes

International Nuclear Information System (INIS)

McLaughlin, D.F.; Lahoda, E.J.; Gass, W.R.; D'Amico, N.

1994-01-01

This document provides a test plan for the conduct of plasma arc vitrification testing by a vendor in support of the Hanford Tank Waste Remediation System (TWRS) Low-Level Waste (LLW) Vitrification Program. The vendor providing this test plan and conducting the work detailed within it [one of seven selected for glass melter testing under Purchase Order MMI-SVV-384212] is the Westinghouse Science and Technology Center (WSTC) in Pittsburgh, PA. WSTC authors of the test plan are D. F. McLaughlin, E. J. Lahoda, W. R. Gass, and N. D'Amico. The WSTC Program Manager for this test is D. F. McLaughlin. This test plan is for Phase I activities described in the above Purchase Order. Test conduct includes melting of glass frit with Hanford LLW Double-Shell Slurry Feed waste simulant in a plasma arc fired furnace

ATF Neutron Irradiation Program Technical Plan

Energy Technology Data Exchange (ETDEWEB)

Geringer, J. W. [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division; Katoh, Yutai [Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States). Materials Science and Technology Division

2016-03-01

The Japan Atomic Energy Agency (JAEA) under the Civil Nuclear Energy Working Group (CNWG) is engaged in a cooperative research effort with the U.S. Department of Energy (DOE) to explore issues related to nuclear energy, including research on accident-tolerant fuels and materials for use in light water reactors. This work develops a draft technical plan for a neutron irradiation program on the candidate accident-tolerant fuel cladding materials and elements using the High Flux Isotope Reactor (HFIR). The research program requires the design of a detailed experiment, development of test vehicles, irradiation of test specimens, possible post-irradiation examination and characterization of irradiated materials and the shipment of irradiated materials to JAEA in Japan. This report discusses the technical plan of the experimental study.

Target Soil Impact Verification: Experimental Testing and Kayenta Constitutive Modeling.

Energy Technology Data Exchange (ETDEWEB)

Broome, Scott Thomas [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Flint, Gregory Mark [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Dewers, Thomas [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States); Newell, Pania [Sandia National Laboratories (SNL-NM), Albuquerque, NM (United States)

2015-11-01

This report details experimental testing and constitutive modeling of sandy soil deformation under quasi - static conditions. This is driven by the need to understand constitutive response of soil to target/component behavior upon impact . An experimental and constitutive modeling program was followed to determine elastic - plastic properties and a compressional failure envelope of dry soil . One hydrostatic, one unconfined compressive stress (UCS), nine axisymmetric compression (ACS) , and one uniaxial strain (US) test were conducted at room temperature . Elastic moduli, assuming isotropy, are determined from unload/reload loops and final unloading for all tests pre - failure and increase monotonically with mean stress. Very little modulus degradation was discernable from elastic results even when exposed to mean stresses above 200 MPa . The failure envelope and initial yield surface were determined from peak stresses and observed onset of plastic yielding from all test results. Soil elasto - plastic behavior is described using the Brannon et al. (2009) Kayenta constitutive model. As a validation exercise, the ACS - parameterized Kayenta model is used to predict response of the soil material under uniaxial strain loading. The resulting parameterized and validated Kayenta model is of high quality and suitable for modeling sandy soil deformation under a range of conditions, including that for impact prediction.

100 Area soil washing treatability test plan

International Nuclear Information System (INIS)

1993-03-01

This test plan describes specifications, responsibilities, and general methodology for conducting a soil washing treatability study as applied to source unit contamination in the 100 Area. The objective ofthis treatability study is to evaluate the use of physical separation systems and chemical extraction methods as a means of separating chemically and radioactively contaminated soil fractions from uncontaminated soil fractions. The purpose of separating these fractions is to minimize the volume of soil requiring permanent disposal. It is anticipated that this treatability study will be performed in two phases of testing, a remedy screening phase and a remedy selection phase. The remedy screening phase consists of laboratory- and bench-scale studies performed by Battelle Pacific Northwest laboratories (PNL) under a work order issued by Westinghouse Hanford Company (Westinghouse Hanford). This phase will be used to provide qualitative evaluation of the potential effectiveness of the soil washing technology. The remedy selection phase, consists of pilot-scale testing performed under a separate service contract to be competitively bid under Westinghouse Hanford direction. The remedy selection phase will provide data to support evaluation of the soil washing technology in future feasibility studies for Interim Remedial Measures (IRMs) or final operable unit (OU) remedies. Performance data from these tests will indicate whether applicable or relevant and appropriate requirements (ARARs) or cleanup goals can be met at the site(s) by application of soil washing. The remedy selection tests wig also allow estimation of costs associated with implementation to the accuracy required for the Feasibility Study

10 CFR Appendix A to Subpart U of... - Sampling Plan for Enforcement Testing of Electric Motors

Science.gov (United States)

2010-01-01

... 10 Energy 3 2010-01-01 2010-01-01 false Sampling Plan for Enforcement Testing of Electric Motors A Appendix A to Subpart U of Part 431 Energy DEPARTMENT OF ENERGY ENERGY CONSERVATION ENERGY EFFICIENCY... to Subpart U of Part 431—Sampling Plan for Enforcement Testing of Electric Motors Step 1. The first...

Experimental test of host specificity in a behaviour-modifying trematode

DEFF Research Database (Denmark)

Hernandez, R.N.; Fredensborg, Brian Lund

2015-01-01

Host behavioural modification by parasites is a common and well-documented phenomenon. However, knowledge on the complexity and specificity of the underlying mechanisms is limited, and host specificity among manipulating parasites has rarely been experimentally verified. We tested the hypothesis...

Experimental tests on ratchet of 304 austenitic steel, at room temperature

International Nuclear Information System (INIS)

Boulais, Jacques; Brouard, Daniel; Lebey, Jacques; Roche, Roland.

1978-09-01

Most of the studies on ratcheting are theoretical and use very rough constitutive equations for the material behavior (perfect plasticity for instance). Most of the available experimental results concern tests on complex structures, and are difficult to interpret. So there is a need for experimental tests on basic structures easy to use to determine the material characteristics. Tests on thin tubular specimen are very interesting because stress, strain and temperature fields are uniform. The primary stress P is an axial tensile one (dead weight), the secondary stress, with ΔQ range, is due to a cyclic angle controled twist. The incremental elongation is obtained as a function of the number of cycles N for different values of P and ΔQ. Diagrams representing the isocurves of cumulated elongation (for a given number of cycles) as a function of P and ΔQ are shown [fr

Test plan for qualification of the S-type fiberglass materials for use as the liquid observation well casing

International Nuclear Information System (INIS)

Parra, S.A.

1995-01-01

This test plan presents the guidelines and requirements for acceptance of the S-type fiberglass material for use as the liquid observation well casing material. The plan for evaluating the physical properties of the candidate fiberglass materials when subjected to radiation, corrosive chemicals, and high temperatures typically found in the waste tanks are outlined. The tests also include tube connection evaluations. Finally, the test plan identifies the participants, their responsibilities, and the schedule for completion of the work

Operational radioactive waste management plan for the Nevada Test Site

International Nuclear Information System (INIS)

1980-11-01

The Operational Radioactive Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements

Program Plan: field radionuclide migration studies in Climax granite

International Nuclear Information System (INIS)

Isherwood, D.; Raber, E.; Coles, D.; Stone, R.

1980-01-01

This Program Plan describes the field radionuclide migration studies we plan to conduct in the Climax granite at the Nevada Test Site. Laboratory support studies are included to help us understand the geochemical and hydrologic processes involved in the field. The Program Plan begins with background information (Section 1) on how this program fits into the National Waste Terminal Storage Program Plan and discusses the needs for field studies of this type. The objectives stated in Section 2 are in direct response to these needs, particularly the need to determine whether laboratory studies accurately reflect actual field conditions and the need for field testing to provide a data base for verification of hydrologic and mass transport models. The technical scope (Section 3) provides a work breakdown structure that integrates the various activities and establishes a base for the technical approach described in Section 4. Our approach combines an interactive system of field and laboratory migration experiments with the use of hydrologic models for pre-test predictions and data interpretation. Section 5 on program interfaces identifies how information will be transferred to other related DOE projects. A schedule of activities and major milestones (Section 6) and the budget necessary to meet the project objectives (Section 7) are included in the Program Plan. Sections 8 and 9 contain brief descriptions of how the technical and program controls will be established and maintained and an outline of our quality assurance program. This program plan is an initial planning document and provides a general description of activities. An Engineering Test Plan containing detailed experimental test plans, an instrumentation plan and equipment design drawings will be published as a separate document

STREAMLINED APPROACH FOR ENVIRONMENTAL RESTORATION PLAN FOR CORRECTIVE ACTION UNIT 116: AREA 25 TEST CELL C FACILITY NEVADA TEST SITE, NEVADA

International Nuclear Information System (INIS)

2006-01-01

This Streamlined Approach for Environmental Restoration Plan identifies the activities required for the closure of Corrective Action Unit 116, Area 25 Test Cell C Facility. The Test Cell C Facility is located in Area 25 of the Nevada Test Site approximately 25 miles northwest of Mercury, Nevada

Critical assessment of precracked specimen configuration and experimental test variables for stress corrosion testing of 7075-T6 aluminum alloy plate

Science.gov (United States)

Domack, M. S.

1985-01-01

A research program was conducted to critically assess the effects of precracked specimen configuration, stress intensity solutions, compliance relationships and other experimental test variables for stress corrosion testing of 7075-T6 aluminum alloy plate. Modified compact and double beam wedge-loaded specimens were tested and analyzed to determine the threshold stress intensity factor and stress corrosion crack growth rate. Stress intensity solutions and experimentally determined compliance relationships were developed and compared with other solutions available in the literature. Crack growth data suggests that more effective crack length measurement techniques are necessary to better characterize stress corrosion crack growth. Final load determined by specimen reloading and by compliance did not correlate well, and was considered a major source of interlaboratory variability. Test duration must be determined systematically, accounting for crack length measurement resolution, time for crack arrest, and experimental interferences. This work was conducted as part of a round robin program sponsored by ASTM committees G1.06 and E24.04 to develop a standard test method for stress corrosion testing using precracked specimens.

Statistical analysis of weld bead geometry in Ti6Al4V laser cladding. Comparison of central composite design and five step full factorial test plan

Energy Technology Data Exchange (ETDEWEB)

Marko, Angelina [Fraunhofer Institute for Production Systems and Design Technology IPK, Berlin (Germany); Graf, Benjamin; Rethmeier, Michael [Fraunhofer Institute for Production Systems and Design Technology IPK, Berlin (Germany). Dept. for Joining and Coating Technology

2017-11-01

The process of laser cladding has become more important during recent years because of its broad application for cladding, repair or additive manufacturing. In the field of mechanical engineering, one use is the repair of turbine blades. For high quality and reliability of the repaired components, it is necessary to adjust the weld bead geometry to the specific repair task. The bead geometry influences the metallurgical bonding and the degree of dilution as well as the formation of defects like pores or cracks. Therefore, it is important to know the effects of the different parameters on the welding bead. A valuable tool to meet this industrial challenge is the design of experiments (DoE). In this context, the user can choose between a huge number of test plans. Greater profit of information is expected by a larger test range. In order to confirm the acceptance, a five-step full factorial test plan is compared to a central composite design in this paper. Moreover, the limits of the experimental range are indicated and restrictions can be derived. As the results show, the essential effects are detected with a full factorial test plan as well as with a central composite design. Merely the effect strength could not always be specified unambiguously. On this account and in consideration of cost efficiency, the use of central compound design is recommended in industrial applications.

Statistical analysis of weld bead geometry in Ti6Al4V laser cladding. Comparison of central composite design and five step full factorial test plan

International Nuclear Information System (INIS)

Marko, Angelina; Graf, Benjamin; Rethmeier, Michael

2017-01-01

The process of laser cladding has become more important during recent years because of its broad application for cladding, repair or additive manufacturing. In the field of mechanical engineering, one use is the repair of turbine blades. For high quality and reliability of the repaired components, it is necessary to adjust the weld bead geometry to the specific repair task. The bead geometry influences the metallurgical bonding and the degree of dilution as well as the formation of defects like pores or cracks. Therefore, it is important to know the effects of the different parameters on the welding bead. A valuable tool to meet this industrial challenge is the design of experiments (DoE). In this context, the user can choose between a huge number of test plans. Greater profit of information is expected by a larger test range. In order to confirm the acceptance, a five-step full factorial test plan is compared to a central composite design in this paper. Moreover, the limits of the experimental range are indicated and restrictions can be derived. As the results show, the essential effects are detected with a full factorial test plan as well as with a central composite design. Merely the effect strength could not always be specified unambiguously. On this account and in consideration of cost efficiency, the use of central compound design is recommended in industrial applications.

Tracer gas diffusion sampling test plan

International Nuclear Information System (INIS)

Rohay, V.J.

1993-01-01

Efforts are under way to employ active and passive vapor extraction to remove carbon tetrachloride from the soil in the 200 West Area an the Hanford Site as part of the 200 West Area Carbon Tetrachloride Expedited Response Action. In the active approach, a vacuum is applied to a well, which causes soil gas surrounding the well to be drawn up to the surface. The contaminated air is cleaned by passage through a granular activated carbon bed. There are questions concerning the radius of influence associated with application of the vacuum system and related uncertainties about the soil-gas diffusion rates with and without the vacuum system present. To address these questions, a series of tracer gas diffusion sampling tests is proposed in which an inert, nontoxic tracer gas, sulfur hexafluoride (SF 6 ), will be injected into a well, and the rates of SF 6 diffusion through the surrounding soil horizon will be measured by sampling in nearby wells. Tracer gas tests will be conducted at sites very near the active vacuum extraction system and also at sites beyond the radius of influence of the active vacuum system. In the passive vapor extraction approach, barometric pressure fluctuations cause soil gas to be drawn to the surface through the well. At the passive sites, the effects of barometric ''pumping'' due to changes in atmospheric pressure will be investigated. Application of tracer gas testing to both the active and passive vapor extraction methods is described in the wellfield enhancement work plan (Rohay and Cameron 1993)

Test/QA plan for the verification testing of selective catalytic reduction control technologies for highway, nonroad use heavy-duty diesel engines

Science.gov (United States)

This ETV test/QA plan for heavy-duty diesel engine testing at the Southwest Research Institute’s Department of Emissions Research (DER) describes how the Federal Test Procedure (FTP), as listed in 40 CFR Part 86 for highway engines and 40 CFR Part 89 for nonroad engines, will be ...

A study on the establishment of severe accident experimental facility

International Nuclear Information System (INIS)

Yoo, Kun Joong; Kim, Sang Baek; Kim, In Sik; Nho, Ki Man; Bark, Rae Joon; Park, Chun Kyeong; Sim, Seok Koo; Lee, Seong Jae; Chung, Moon Ki; Cho, Yeong Ro; Chun, Shee Yeong

1994-07-01

Significant progress has been achieved during this year of the project. Planned DCH experiments on the sensitivity of the cavity geometry factors and the cavity capture volume effects were performed using the HPME facility for Kori-1/2 and YGN-3/4 cavity scale models. The Crust Formation Test Facility has been completed. Preliminary calculations were performed to predict test results. The experiments of the crust formation on the simulant and its heat transfer characteristic were performed to investigate the effects of coolant injection methods, bottom heating boundary surface temperatures, coolant temperatures and coolant flow rates. The design of the FCI Test Facility has been completed and the procurement of the materials is in progress. Also, the steam condensation experiment on the vertical containment walls and the research on the development of measuring techniques of the particle sizes and velocities are in progress as planned. Through international research collaboration with USNRC and CEA Cadarache, information of the experimental research on the severe fuel damage has been gathered and analyzed. Preliminary planning of the second phase tests has been launched this year. This study proposes the scope of the second phase and the strategy to implement the proposed second phase experimental program. This study also proposes a strategy to establish building blocks and infrastructure for the severe accident research in Korea. (Author)

Actions needed for RA reactor exploitation - I-IV, Part II, Design project VI-SA 1, Experimental loop for testing the EL-4 reactor fuel elements in the central vertical experimental channel of the RA reactor in Vinca; Radovi za potrebe eksploatacije reaktora RA - I-IV, II Deo, Predprojekat VI-SA 1, Petlja za ispitivanje gorivnih elemenata reaktora EL-4 u centralnom vertikalnom eksperimentalnom kanalu reaktora RA u Vinci

Energy Technology Data Exchange (ETDEWEB)

Novakovic, M [Institute of Nuclear Sciences Boris Kidric, Vinca, Beograd (Serbia and Montenegro)

1961-12-15

The objective of installing the VISA-1 loop was testing the fuel elements of the EL-4 reactor. The fuel elements planned for testing are natural UO{sub 2} with beryllium cladding, cooled by CO{sub 2} under nominal pressure of 60 at and temperature 600 deg C. central vertical experimental channel of the RA reactor was chosen for installing a test loop cooled by CO{sub 2}. This report contains the detailed design project of the testing loop with the control system and safety analysis of the planned experiment.

In situ impulse test: an experimental and analytical evaluation of data interpretation procedures

International Nuclear Information System (INIS)

1975-08-01

Special experimental field testing and analytical studies were undertaken at Fort Lawton in Seattle, Washington, to study ''close-in'' wave propagation and evaluate data interpretation procedures for a new in situ impulse test. This test was developed to determine the shear wave velocity and dynamic modulus of soils underlying potential nuclear power plant sites. The test is different from conventional geophysical testing in that the velocity variation with strain is determined for each test. In general, strains between 10 -1 and 10 -3 percent are achieved. The experimental field work consisted of performing special tests in a large test sand fill to obtain detailed ''close-in'' data. Six recording transducers were placed at various points on the energy source, while approximately 37 different transducers were installed within the soil fill, all within 7 feet of the energy source. Velocity measurements were then taken simultaneously under controlled test conditions to study shear wave propagation phenomenology and help evaluate data interpretation procedures. Typical test data are presented along with detailed descriptions of the results

Gas liquid sampling for closed canisters in KW Basin - test plan

International Nuclear Information System (INIS)

Pitkoff, C.C.

1995-01-01

Test procedures for the gas/liquid sampler. Characterization of the Spent Nuclear Fuel, SNF, sealed in canisters at KW-Basin is needed to determine the state of storing SNF wet. Samples of the liquid and the gas in the closed canisters will be taken to gain characterization information. Sampling equipment has been designed to retrieve gas and liquid from the closed canisters in KW basin. This plan is written to outline the test requirements for this developmental sampling equipment

48 CFR 252.219-7004 - Small business subcontracting plan (test program).

Science.gov (United States)

2010-10-01

... 48 Federal Acquisition Regulations System 3 2010-10-01 2010-10-01 false Small business... AND CONTRACT CLAUSES Text of Provisions And Clauses 252.219-7004 Small business subcontracting plan (test program). As prescribed in 219.708(b)(1)(B), use the following clause: Small Business...

Environmental Monitoring Plan, Nevada Test Site and support facilities

International Nuclear Information System (INIS)

1991-11-01

This Operational Area Monitoring Plan for environmental monitoring, is for EG ampersand G Energy Measurements, Inc. (EG ampersand G/EM) which operates several offsite facilities in support of activities at the Nevada Test Site (NTS). These facilities include: (1) Amador Valley Operations (AVO), Pleasanton, California; (2) Kirtland Operations (KO), Kirtland Air Force base, Albuquerque, New Mexico (KAFB); (3) Las Vegas Area Operations (LVAO), Remote Sensing Laboratory (RSL), and North Las Vegas (NLV) Complex at Nellis Air Force Base (NAFB), North Las Vegas, Nevada; (4) Los Alamos Operations (LAO), Los Alamos, New Mexico; (5) Santa Barbara Operations (SBO), Goleta, California; (6) Special Technologies Laboratory (STL), Santa Barbara, California; (7) Washington Aerial Measurements Department (WAMD), Andrews Air Force Base, Maryland; and, (8) Woburn Cathode Ray Tube Operations (WCO), Woburn, Massachusetts. Each of these facilities has an individual Operational Area Monitoring Plan, but they have been consolidated herein to reduce redundancy

Contraceptive social marketing: a continuous cycle of planning, testing and evaluating.

Science.gov (United States)

1985-01-01

This article outlines the contraceptive marketing process used by the Social Marketing for Change (SOMARC) project. The 1st stage of the process involves analysis of the market, the consumer, and the social marketing organization's capabilities. In the 2nd stage, planning, data collected in the analysis stage are used to define objectives, segment target markets, and devise strategies for each element in the marketing mix. In the 3rd stage, all the elements in the marketing mix are developed and tested (e.g. product concepts, pricing, packaging, communication messages) and refined on the basis of test results. In stage 4, the action plan is implemented and marketing progress and institutional performance are monitored. Stage 5 includes an assessment of in-market effectiveness in terms of responses from consumers, retailers, and health professionals. The last stage feeds back to the 1st. All the reviewed data are recycled into analysis to begin again the continuous process of refinement and improvement.

What does an experimental test of quantum contextuality prove or disprove?

International Nuclear Information System (INIS)

Winter, Andreas

2014-01-01

The possibility of experimentally testing the Bell–Kochen–Specker theorem is investigated critically, following the demonstrations by Meyer, Kent, and Clifton–Kent that the predictions of quantum mechanics are indistinguishable (up to arbitrary precision) from those of a non-contextual model, and the subsequent debate about the extent to which these models are actually classical or non-contextual. The present analysis starts from a careful consideration of these ‘finite-precision’ approximations. A stronger condition for non-contextual models, dubbed ontological faithfulness, is exhibited. It is shown that this allows us to approximately formulate the constraints in Bell–Kochen–Specker theorems, such as to render the usual proofs robust. Consequently, one can experimentally test to finite precision ontologically faithful non-contextuality, and thus experimentally refute explanations from this smaller class. We include a discussion of the relation of ontological faithfulness to other proposals to overcome the finite precision objection. This article is part of a special issue of Journal of Physics A: Mathematical and Theoretical devoted to ‘50 years of Bell’s theorem’. (paper)

Pilot-scale treatability test plan for the 100-HR-3 operable unit

International Nuclear Information System (INIS)

1994-08-01

This document presents the treatability test plan for pilot-scale pump-and-treat testing at the 100-HR-3 Operable Unit. The test will be conducted in fulfillment of interim Milestone M-15-06E to begin pilot-scale pump-and-treat operations by August 1994. The scope of the test was determined based on the results of lab/bench-scale tests (WHC 1993a) conducted in fulfillment of Milestone M-15-06B. These milestones were established per agreement between the U.S. Department of Energy (DOE), the Washington State Department of Ecology and the U.S. Environmental Protection Agency (EPA), and documented on Hanford Federal of Ecology Facility Agreement and Consent Order Change Control Form M-15-93-02. This test plan discusses a pilot-scale pump-and-treat test for the chromium plume associated with the D Reactor portion of the 100-HR-3 Operable Unit. Data will be collected during the pilot test to assess the effectiveness, operating parameters, and resource needs of the ion exchange (IX) pump-and-treat system. The test will provide information to assess the ability to remove contaminants by extracting groundwater from wells and treating extracted groundwater using IX. Bench-scale tests were conducted previously in which chromium VI was identified as the primary contaminant of concern in the 100-D reactor plume. The DOWEX 21K trademark resin was recommended for pilot-scale testing of an IX pump-and-treat system. The bench-scale test demonstrated that the system could remove chromium VI from groundwater to concentrations less than 50 ppb. The test also identified process parameters to monitor during pilot-scale testing. Water will be re-injected into the plume using wells outside the zone of influence and upgradient of the extraction well

Short-Run Contexts and Imperfect Testing for Continuous Sampling Plans

Directory of Open Access Journals (Sweden)

Mirella Rodriguez

2018-04-01

Full Text Available Continuous sampling plans are used to ensure a high level of quality for items produced in long-run contexts. The basic idea of these plans is to alternate between 100% inspection and a reduced rate of inspection frequency. Any inspected item that is found to be defective is replaced with a non-defective item. Because not all items are inspected, some defective items will escape to the customer. Analytical formulas have been developed that measure both the customer perceived quality and also the level of inspection effort. The analysis of continuous sampling plans does not apply to short-run contexts, where only a finite-size batch of items is to be produced. In this paper, a simulation algorithm is designed and implemented to analyze the customer perceived quality and the level of inspection effort for short-run contexts. A parameter representing the effectiveness of the test used during inspection is introduced to the analysis, and an analytical approximation is discussed. An application of the simulation algorithm that helped answer questions for the U.S. Navy is discussed.

Experimental halls workshop summary

International Nuclear Information System (INIS)

Thorndike, A.

1976-01-01

On May 26 and 27, 1976, approximately 50 people met for an informal workshop on plans for experimental halls for ISABELLE. Plans as they exist in the May 1976 version of the ISABELLE proposal were presented. Discussions were held on the following four general topics by separate working groups: (1) pros and cons of open areas as compared with enclosed halls; (2) experimental hall needs of ep, anti pp, and other options; (3) hall for the lepton detector; and (4) hall for the hadron spectrometer. The planning for experimental halls at PEP, the hall for the lepton detector, the hadron spectrometer, and open areas are discussed

Test plan for reactions between spent fuel and J-13 well water under unsaturated conditions

International Nuclear Information System (INIS)

Finn, P.A.; Wronkiewicz, D.J.; Hoh, J.C.; Emery, J.W.; Hafenrichter, L.D.; Bates, J.K.

1993-01-01

The Yucca Mountain Site Characterization Project is evaluating the long-term performance of a high-level nuclear waste form, spent fuel from commercial reactors. Permanent disposal of the spent fuel is possible in a potential repository to be located in the volcanic tuff beds near Yucca Mountain, Nevada. During the post-containment period the spent fuel could be exposed to water condensation since of the cladding is assumed to fail during this time. Spent fuel leach (SFL) tests are designed to simulate and monitor the release of radionuclides from the spent fuel under this condition. This Test Plan addresses the anticipated conditions whereby spent fuel is contacted by small amounts of water that trickle through the spent fuel container. Two complentary test plans are presented, one to examine the reaction of spent fuel and J-13 well water under unsaturated conditions and the second to examine the reaction of unirradiated UO 2 pellets and J-13 well water under unsaturated conditions. The former test plan examines the importance of the water content, the oxygen content as affected by radiolysis, the fuel burnup, fuel surface area, and temperature. The latter test plant examines the effect of the non-presence of Teflon in the test vessel

TREATABILITY TEST PLAN FOR DEEP VADOSE ZONE REMEDIATION AT THE HANFORD'S SITE CENTRAL PLATEAU

International Nuclear Information System (INIS)

PETERSEN SW; MORSE JG; TRUEX MJ; LAST GV

2007-01-01

A treatability test plan has been prepared to address options for remediating portions of the deep vadose zone beneath a portion of the U.S. Department of Energy's (DOE's) Hanford Site. The vadose zone is the region of the subsurface that extends from the ground surface to the water table. The overriding objective of the treatability test plan is to recommend specific remediation technologies and laboratory and field tests to support the Comprehensive Environmental Response, Compensation, and Liability Act of 1980 and Resource Conservation and Recovery Act of 1976 remedial decision-making process in the Central Plateau of the Hanford Site. Most of the technologies considered involve removing water from the vadose zone or immobilizing the contaminants to reduce the risk of contaminating groundwater. A multi-element approach to initial treatability testing is recommended, with the goal of providing the information needed to evaluate candidate technologies. The proposed tests focus on mitigating two contaminants--uranium and technetium. Specific technologies are recommended for testing at areas that may affect groundwater in the future, but a strategy to test other technologies is also presented

Quiet Clean Short-Haul Experimental Engine (QCSEE) ball spline pitch-change mechanism whirligig test report

Science.gov (United States)

1978-01-01

The component testing of a ball spline variable pitch mechanism is described including a whirligig test. The variable pitch actuator successfully completed all planned whirligig tests including a fifty cycle endurance test at actuation rates up to 125 deg per second at up to 102 percent fan speed (3400 rpm).

FENIX [Fusion ENgineering International eXperimental]: A test facility for ITER [International Thermonuclear Experimental Reactor] and other new superconducting magnets

International Nuclear Information System (INIS)

Slack, D.S.; Patrick, R.E.; Miller, J.R.

1990-01-01

The Fusion ENgineering International eXperimental (FENIX) Test Facility which is nearing completion at Lawrence Livermore National Laboratory, is a 76-t set of superconducting magnets housed in a 4-m-diameter cryostat. It represents a significant step toward meeting the testing needs for the development of superconductors appropriate for large-scale magnet applications such as the International Thermonuclear Experimental Reactor (ITER). The magnet set is configured to allow radial access to the 0.4-m-diameter high-field region where maximum fields up to 14 T will be provided. The facility is fitted with a thermally isolated test well with a port to the high-field region that allows insertion and removal of test conductors without disturbing the cryogenic environment of the magnets. It is expected that the facility will be made available to magnet developers internationally, and this paper discusses its general design features, its construction, and its capabilities

Physical Education Experimental Program to Test the Effect on Perceived Competence

OpenAIRE

Edin Brankovic; Muriz Hadzikadunic

2017-01-01

The first purpose of this study was to test effect of multidisciplinary and holistic experimental program (EP) in physical education program effect on the soul need perceived competence. The second purpose of this study was to analyse the relationship between attitudes of perceived competence in the experimental group before and after the application of program, mostly due the theoretical reason that perceived competence is predictor of Flow. The data was collected from 74 students of the 8th...

ERG and GRG review of the draft of ''preliminary test plan for in situ testing from an exploratory shaft in salt - October 1983''

International Nuclear Information System (INIS)

Kalia, H.N.

1986-03-01

The Engineering Review Group (ERG) and Geologic Review Group (GRG) were established by the Office of Nuclear Waste Isolation (ONWI) to help evaluate engineering- and geologic-related issues in the US Department of Energy's nuclear waste repository program. The January 1984 meeting of the ERG and GRG reviewed the In Situ Test Plan (ISTP) titled ''Preliminary Test Plan for In Situ Testing From an Exploratory Shaft in Salt - October 1983.'' This report documents the ERG's and GRG's comments and recommendations on this subject and the ONWI responses to the specific points raised by the ERG and GRG. 6 refs., 2 figs., 1 tab

Experimental results of some cluster tests in NSRR

International Nuclear Information System (INIS)

Kobayashi, Shinsho; Ohnishi, Nobuaki; Yoshimura, Tomio; Lussie, W.G.

1978-01-01

The NSRR programme is in progress in JAERI using a pulsed reactor to evaluate the behavior of reactor fuels under reactivity accident conditions. This report describes briefly the experimental results and preliminary analysis of two cluster tests. In the cluster configuration of five fuel rods, the power distribution in outer fuel rods are not symmetric due to neutron absorption in central fuel rod. The cladding temperature on the exterior boundaries of the cluster is higher than that in interior. Good agreement was obtained between the calculated and measured cladding temperature histories. In the 3.8$ excess reactivity test, cluster averaged energy deposition of 237 cal/g.UO 2 , cladding melting and deformation were limited to the portions of the fuel rods that were on the exterior boundaries of the cluster. (auth.)

Acceptance test plan for the Waste Information Control System

International Nuclear Information System (INIS)

Flynn, D.F.

1994-01-01

This document describes the acceptance test plan for the WICS system. The Westinghouse Hanford Company (WHC) Hazardous Material Control Group (HMC) of the 222-S Laboratory has requested the development of a system to help resolve many of the difficulties associated with tracking and data collection of containers and drums of waste. This system has been identified as Waste Information and Control System (WICS). The request for developing and implementing WICS has been made to the Automation and Simulation Engineering Group (ASE)

Validation of a Wave-Body Interaction Model by Experimental Tests

DEFF Research Database (Denmark)

Ferri, Francesco; Kramer, Morten; Pecher, Arthur

2013-01-01

Within the wave energy field, numerical simulation has recently acquired a worldwide consent as being a useful tool, besides physical model testing. The main goal of this work is the validation of a numerical model by experimental results. The numerical model is based on a linear wave-body intera...

Integrated corridor management initiative : demonstration phase evaluation, Dallas air quality test plan.

Science.gov (United States)

2012-08-01

This report presents the test plan for conducting the Air Quality Analysis for the United States : Department of Transportation (U.S. DOT) evaluation of the Dallas U.S. 75 Integrated Corridor : Management (ICM) Initiative Demonstration. The ICM proje...

Experimental test of the renormalizability consequences of the standard electroweak theory

International Nuclear Information System (INIS)

Bardin, D.Yu.

1984-01-01

The present status of the one-loop radiative corrections calculations in the standard electroweak theory is discussed. The possibilities of experimental tests of the higher order predictions of the standard theory is analysed in view of recent data, inclu-ing CERN p anti pcolcider data on Msub(W) and Msub(Z) measurement. The perspectives of these tests in the near future experiments are discussed

Detailed leak detection test plan and schedule for the Oak Ridge National Laboratory LLLW active pipelines

International Nuclear Information System (INIS)

Douglas, D.G.; Starr, J.W.; Juliano, T.M.; Maresca, J.W. Jr.

1993-09-01

This document provides a detailed leak detection test plan and schedule for leak testing many of the pipelines that comprise the active portion of the liquid low-level waste (LLLW) system at the Oak Ridge National Laboratory (ORNL). This plan was prepared in response to the requirements of the Federal Facility Agreement (FFA) between the US Department of Energy (DOE) and two other agencies, the US Environmental Protection Agency (EPA) and the Tennessee Department of Environment and Conservation (TDEC). The LLLW system is an interconnected complex of tanks and pipelines. The FFA distinguishes four categories of tank and pipeline systems within this complex: new systems (Category A), doubly contained systems (Category B), singly contained systems (Category C), and inactive systems (Category D). The FFA specifically requires leak testing of the Category C systems. This plan and schedule addresses leak testing of the Category C pipelines and those doubly contained pipelines that do not fully meet the requirements for secondary containment as listed in the FFA

Experimental Tests of Quantum Mechanics: Pauli Exclusion Principle and Spontaneous Collapse Models

CERN Document Server

Petrascu, Catalina Curceanu; Bragadireanu, Mario; Clozza, Alberto; Guaraldo, Carlo; Iliescu, Mihai; Rizzo, Alessandro; Vidal, Antonio Romero; Scordo, Alessandro; Sirghi, Diana Laura; Sirghi, Florin; Sperandio, Laura; Doce, Oton Vazquez; Bassi, Angelo; Donadi, Sandro; Milotti, Edoardo; Laubenstein, Matthias; Bertolucci, Sergio; Bragadireanu, Mario; Curceanu, Catalina; Pietreanu, Dorel; Ponta, Titus; Cargnelli, Michael; Ishiwatari, Tomoichi; Marton, Johann; Widmann, Eberhard; Zmeskal, Johann; Matteo, Sergio di; Egger, Jean Pierre

2014-01-01

The Pauli exclusion principle (PEP), as a consequence or the spin-statistics connection, is one of the basic principles of the modern physics. Being at the very basis of our understanding of matter, it spurs a lively debate on its possible limits, deeply rooted as it is in the very foundations of Quantum Field Theory. The VIP (VIolation of the Pauli exclusion principle) experiment is searching for a possible small violation of the PEP for electrons, using the method of searching for Pauli Exclusion Principle forbidden atomic transitions in copper. We describe the experimental method and the obtained results; we briefly present future plans to go beyond the actual limit by upgrading the experiment using vetoed new spectroscopic fast Silicon Drift Detectors. We also mention the possibility of using a similar experimental technique to search for possible X-rays generated in the spontaneous collapse models of quantum mechanics.

Experimental tests of gauge theories

International Nuclear Information System (INIS)

Haidt, D.

1984-11-01

This series of five lectures is intended to provide the experimental basis to the theoretical courses on gauge symmetries delivered by C. Jarlskog and R. Petronzio. The framework is the standard model. The experimental material is taken mainly from lepton-hadron and e + e - -experiments. (orig./HSI)

Project W-151 flexible receiver radiation detector system acceptance test plan. Revision 1

International Nuclear Information System (INIS)

Troyer, G.L.

1994-01-01

The attached document is the Acceptance Test Plan for the portion of Project W-151 dealing with acceptance of gamma-ray detectors and associated electronics manufactured at the Idaho National Engineering Laboratory (INEL). The document provides a written basis for testing the detector system, which will take place in the 305 building (300 Area)

Examination plan for the soils and low-level radioactive waste forms of the NRC field testing lysimeters

International Nuclear Information System (INIS)

McConnell, J.W. Jr.; Rogers, R.D.; Jastrow, J.D.

1996-01-01

The Field Lysimeter Investigations: Low-Level Waste Data Base Development Program is obtaining information on the performance of radioactive waste forms. These experiments were recently shut down and have been examined in accordance with a detailed waste form and soil sampling plan. Ion-exchange resins from a commercial nuclear power station were solidified into waste forms using portland cement and vinyl ester-styrene. These waste forms were tested to (a) obtain information on performance of waste forms in typical disposal environments, (b) compare field results with bench leach studies, (c) develop a low-level waste data base for use in performance assessment source term calculations, and (d) apply the DUST computer code to compare predicted cumulative release to actual field data. The program, funded by the Nuclear Regulatory Commission (NRC), includes observed radionuclide releases from waste forms at two test sites over 10 years of successful operation. Lysimeters are ideal systems for obtaining actual field test data because, when properly designed and operated, they can be used to isolate soil and waste systems under actual environmental conditions. The purpose of this paper is to present the experimental plan for the examination of the waste forms and soils of the two lysimeter arrays, which have now been shut down. Vertical soil cores have been taken from the soil columns and will be analyzed with radiochemistry to define movement of radionuclides after release from the waste forms. A comparison is made of the DUST-predicted releases to those previously determined and reported from the lysimeter leachate analyses. That comparison uses new partition coefficients (Kd) recently obtained from laboratory analysis of the lysimeter soils and sand. Those DUST code results also will be compared to actual radionuclide movements through the soil columns as determined from soil core analysis

Test Plan for Long-Term Operation of a Ten-Cell High Temperature Electrolysis Stack

International Nuclear Information System (INIS)

James E. O'Brien; Carl M. Stoots; J. Stephen Herring

2008-01-01

This document defines a test plan for a long-term (2500 Hour) test of a ten-cell high-temperature electrolysis stack to be performed at INL during FY09 under the Nuclear Hydrogen Initiative. This test was originally planned for FY08, but was removed from our work scope as a result of the severe budget cuts in the FY08 NHI Program. The purpose of this test is to evaluate stack performance degradation over a relatively long time period and to attempt to identify some of the degradation mechanisms via post-test examination. This test will be performed using a planar ten-cell Ceramatec stack, with each cell having dimensions of 10 cm x 10 cm. The specific makeup of the stack will be based on the results of a series of shorter duration ten-cell stack tests being performed during FY08, funded by NGNP. This series of tests was aimed at evaluating stack performance with different interconnect materials and coatings and with or without brazed edge rails. The best performing stack from the FY08 series, in which five different interconnect/coating/edge rail combinations were tested, will be selected for the FY09 long-term test described herein

Reliability demonstration test planning using bayesian analysis

International Nuclear Information System (INIS)

Chandran, Senthil Kumar; Arul, John A.

2003-01-01

In Nuclear Power Plants, the reliability of all the safety systems is very critical from the safety viewpoint and it is very essential that the required reliability requirements be met while satisfying the design constraints. From practical experience, it is found that the reliability of complex systems such as Safety Rod Drive Mechanism is of the order of 10 -4 with an uncertainty factor of 10. To demonstrate the reliability of such systems is prohibitive in terms of cost and time as the number of tests needed is very large. The purpose of this paper is to develop a Bayesian reliability demonstrating testing procedure for exponentially distributed failure times with gamma prior distribution on the failure rate which can be easily and effectively used to demonstrate component/subsystem/system reliability conformance to stated requirements. The important questions addressed in this paper are: With zero failures, how long one should perform the tests and how many components are required to conclude with a given degree of confidence, that the component under test, meets the reliability requirement. The procedure is explained with an example. This procedure can also be extended to demonstrate with more number of failures. The approach presented is applicable for deriving test plans for demonstrating component failure rates of nuclear power plants, as the failure data for similar components are becoming available in existing plants elsewhere. The advantages of this procedure are the criterion upon which the procedure is based is simple and pertinent, the fitting of the prior distribution is an integral part of the procedure and is based on the use of information regarding two percentiles of this distribution and finally, the procedure is straightforward and easy to apply in practice. (author)

ENGINEERING DESIGN OPTIMIZATION OF HEEL TESTING EQUIPMENT IN THE EXPERIMENTAL VALIDATION OF SAFE WALKING

Directory of Open Access Journals (Sweden)

Cristiano Fragassa

2017-06-01

Full Text Available Experimental test methods for the evaluation of the resistance of heels of ladies' shoes in the case of impact loads are fully defined by International Organization for Standardization (ISO procedures that indicate all the conditions of experiment. A first Standard (ISO 19553 specifies the test method for determining the strength of the heels in the case of single impact. The result offers a valuation of the liability to fail under the sporadic heavy blows. A second Standard (ISO 19556 details a method for testing the capability of heels of women' shoes to survive to the repetition of small impacts provoked by normal walking. These Standards strictly define the features for two different testing devices (with specific materials, geometries, weights, etc. and all the experimental procedures to be followed during tests. On the contrary, this paper describes the technical solutions adopted to design one single experimental device able to perform impact testing of heels in both conditions. Joining the accuracy of mechanic movements with the speed of an electronic control system, a new and flexible equipment for the complete characterization of heels respect to (single or fatigue impacts was developed. Moreover a new level of performances in experimental validation of heel resistance was introduced by the versatility of the user-defined software control programs, able to encode every complex time-depending cycle of impact loads. Dynamic simulations permitted to investigate the impacts on heel in different conditions of testing, optimizing the machine design. The complexity of real stresses on shoes during an ordinary walk and in other common situations (as going up and downstairs was considered for a proper dimensioning.

SOFC regulation at constant temperature: Experimental test and data regression study

International Nuclear Information System (INIS)

Barelli, L.; Bidini, G.; Cinti, G.; Ottaviano, A.

2016-01-01

Highlights: • SOFC operating temperature impacts strongly on its performance and lifetime. • Experimental tests were carried out varying electric load and feeding mixture gas. • Three different anodic inlet gases were tested maintaining constant temperature. • Cathodic air flow rate was used to maintain constant its operating temperature. • Regression law was defined from experimental data to regulate the air flow rate. - Abstract: The operating temperature of solid oxide fuel cell stack (SOFC) is an important parameter to be controlled, which impacts the SOFC performance and its lifetime. Rapid temperature change implies a significant temperature differences between the surface and the mean body leading to a state of thermal shock. Thermal shock and thermal cycling introduce stress in a material due to temperature differences between the surface and the interior, or between different regions of the cell. In this context, in order to determine a control law that permit to maintain constant the fuel cell temperature varying the electrical load and the infeed fuel mixture, an experimental activity were carried out on a planar SOFC short stack to analyse stack temperature. Specifically, three different anodic inlet gas compositions were tested: pure hydrogen, reformed natural gas with steam to carbon ratio equal to 2 and 2.5. By processing the obtained results, a regression law was defined to regulate the air flow rate to be provided to the fuel cell to maintain constant its operating temperature varying its operating conditions.

Survey of experimental tests of the IBA model

International Nuclear Information System (INIS)

Casten, R.F.

1980-01-01

A survey of experimental tests of the Interacting Boson Approximation (IBA) Model is presented covering even and odd mass nuclei in the region from A approx. 80 to A approx. 230. Both positive and negative parity states with both high and low spin are discussed. Topics included concern energy levels, electromagnetic transition rates, two nucleon transfer and inelastic scattering. Special attention is given to nuclear symmetries and transitional regions. Comparison with other models is made where appropriate. The distinction between IBA-1 and IBA-2 is discussed including their respective areas of applicability

Test plan using the HTTR for commercialization of GTHTR300C

International Nuclear Information System (INIS)

Tachibana, Yukio; Sakaba, Nariaki; Ohashi, Hirofumi; Sato, Hiroyuki; Ueta, Shohei; Aihara, Jun; Goto, Minoru; Sumita, Junya; Shibata, Taiju; Takamatsu, Kuniyoshi; Inagaki, Yoshiyuki; Kunitomi, Kazuhiko; Nishihara, Tetsuo; Hamamoto, Shimpei; Iyoku, Tatsuo

2010-02-01

The High Temperature Engineering Test Reactor (HTTR) is the first High Temperature Gas-cooled Reactor (HTGR) built at the Oarai Research and Development Center of JAEA with thermal power of 30 MW and the maximum reactor outlet coolant temperature of 950degC. The HTTR achieved the first criticality in 1998, the reactor outlet coolant temperature of 950degC in 2004, and 30 days continuous operation in 2007. Since 2002, safety demonstration tests including reactivity insertion tests and coolant flow reduction tests have been conducted to show inherent safety features of the HTGRs by using the HTTR. This report describes full scope of the future feasible test plan mainly using the HTTR. The test items cover fuel performance and radionuclide transport, core physics, reactor thermal hydraulics and plant dynamics, and reactor operations, maintenance, control, etc. The test results will be utilized for realization of Japan's commercial Very High Temperature Reactor (VHTR) system, GTHTR300C. (author)

Operational radioactive defense waste management plan for the Nevada Test Site

International Nuclear Information System (INIS)

1981-07-01

The Operational Radioactive Defense Waste Management Plan for the Nevada Test Site establishes procedures and methods for the safe shipping, receiving, processing, disposal, and storage of radioactive waste. Included are NTS radioactive waste disposition program guidelines, procedures for radioactive waste management, a description of storage and disposal areas and facilities, and a glossary of specifications and requirements