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Test facilities for future linear colliders

Description: During the past several years there has been a tremendous amount of progress on Linear Collider technology world wide. This research has led to the construction of the test facilities described in this report. Some of the facilities will be complete as early as the end of 1996, while others will be finishing up around the end 1997. Even now there are extensive tests ongoing for the enabling technologies for all of the test facilities. At the same time the Linear Collider designs are quite mature now and the SLC is providing the key experience base that can only come from a working collider. All this taken together indicates that the technology and accelerator physics will be ready for a future Linear Collider project to begin in the last half of the 1990s.
Date: December 1, 1995
Creator: Ruth, R.D.
Partner: UNT Libraries Government Documents Department

Study of Abnormal Vertical Emittance Growth in ATF Extraction Line

Description: Since several years, the vertical beam emittance measured in the Extraction Line (EXT) of the Accelerator Test Facility (ATF) at KEK, that will transport the electron beam from the ATF Damping Ring (DR) to the future ATF2 Final Focus beam line, is significantly larger than the emittance measured in the DR itself, and there are indications that it grows rapidly with increasing beam intensity. This longstanding problem has motivated studies of possible sources of this anomalous emittance growth. One possible contribution is non-linear magnetic fields in the extraction region experimented by the beam while passing off-axis through magnets of the DR during the extraction process. In this paper, simulations of the emittance growth are presented and compared to observations. These simulations include the effects of predicted non-linear field errors in the shared DR magnets and orbit displacements from the reference orbit in the extraction region. Results of recent measurements using closed orbit bumps to probe the relation between the extraction trajectory and the anomalous emittance growth are also presented.
Date: November 4, 2011
Creator: Alabau, M.; Faus-Golfe, A.; /Valencia U., IFIC; Alabau, M.; Bambade, P.; Brossard, J. et al.
Partner: UNT Libraries Government Documents Department

Study for ILC Damping Ring at KEKB

Description: ILC damping ring consists of very low emittance electron and positron storage rings. It is necessary for ILC damping ring to study electron cloud effects in such low emittance positron ring. We propose a low emittance operation of KEKB to study the effects.
Date: November 4, 2011
Creator: Flanagan, J.W.; Fukuma, H.; Kanazawa, K.I.; Koiso, H.; Masuzawa, M.; Ohmi, Kazuhito et al.
Partner: UNT Libraries Government Documents Department

Threshold Assessment: Definition of Acceptable Sites as Part of Site Selection for the Japanese HLW Program

Description: For the last ten years, the Japanese High-Level Nuclear Waste (HLW) repository program has focused on assessing the feasibility of a basic repository concept, which resulted in the recently published H12 Report. As Japan enters the implementation phase, a new organization must identify, screen and choose potential repository sites. Thus, a rapid mechanism for determining the likelihood of site suitability is critical. The threshold approach, described here, is a simple mechanism for defining the likelihood that a site is suitable given estimates of several critical parameters. We rely on the results of a companion paper, which described a probabilistic performance assessment simulation of the HLW reference case in the H12 report. The most critical two or three input parameters are plotted against each other and treated as spatial variables. Geostatistics is used to interpret the spatial correlation, which in turn is used to simulate multiple realizations of the parameter value maps. By combining an array of realizations, we can look at the probability that a given site, as represented by estimates of this combination of parameters, would be good host for a repository site.
Date: October 3, 2000
Creator: McKenna, S.A.; Wakasugi, Keiichiro; Webb, E.K.; Makino, Hitoshi; Ishihara, Yoshinao, Ijiri, Yuji; Sawada, Atsushi et al.
Partner: UNT Libraries Government Documents Department

Development of the JAERI (Japan Atomic Energy Research Institute) fuel cleanup system for tests at the Tritium Systems Test Assembly

Description: Tritium Process Laboratory (TPL) at the Japan Atomic Energy Research Institute (JAERI) has developed the Fuel Cleanup System (FCU) which accepts simulated fusion reactor exhaust and produces pure hydrogen isotopes and tritium-free waste. The major components are: a palladium diffuser, a catalytic reactor, cold traps, a ceramic electrolysis cell, and zirconium-cobalt beds. In 1988, an integrated loop of the FCU process was installed in the TPL and a number of hot'' runs were performed to study the system characteristics and improve system performance. Under the US-Japan collaboration program, the JAERI Fuel Cleanup System'' (JFCU) was designed and fabricated by JAERI/TPL for testing at the Tritium Systems Test Assembly (TSTA) in Los Alamos National Laboratory as a major subsystem of the simulated fusion fuel cycle. The JFCU was installed in the TSTA in early 1990.
Date: January 1, 1990
Creator: Konishi, S.; Inoue, M.; Hayashi, T.; Okuno, K.; Naruse, Y. (Japan Atomic Energy Research Inst., Tokai, Ibaraki (Japan)); Barnes, J.W. et al.
Partner: UNT Libraries Government Documents Department

Comparison of H sup minus and D sup minus production in a magnetically filtered multicusp source

Description: A JAERI negative ion source was tested at LBL as part of the US-Japan Fusion Cooperation Program. By varying the strength of magnetic filter from 450 to 930 Gauss-cm, we compared production, transport, and extraction of the negative ions. The maximum current densities, which obtained at the corresponding optimum filter strength for each gas species, were 10.4 mA/cm{sup 2} for H{sup {minus}} and 8.4 mA/cm{sup 2} for D{sup {minus}} at arc discharges of 40 kW. The ratio of the ion current densities (J{sub D}{minus}/J{sub H}{minus}) is about 0.8, which is higher than 1/{radical}2. The electron to negative ion ration was 13 for hydrogen and 38 for deuterium at the corresponding optimum filter strength. The higher ratio in deuterium is probably due to higher space potential of deuterium plasma by a few volts. 9 refs., 7 figs.
Date: April 1, 1989
Creator: Inoue, T.; Ackerman, G.D.; Cooper, W.S.; Hanada, M.; Kwan, J.W.; Ohara, Y. et al.
Partner: UNT Libraries Government Documents Department

State of H sup minus source development

Description: The status of H{sup {minus}} ion source development is reviewed. There are new and important advancement in both surface- and volume-production H{sup {minus}} sources. It is shown that high brightness H{sup {minus}} beams are generated by ion sources which utilize both surface and volume production processes. 27 refs., 6 figs.
Date: May 1, 1991
Creator: Leung, K.N.
Partner: UNT Libraries Government Documents Department

Current US activities and directions in shielding technology for liquid-metal-cooled reactors

Description: The US shielding development program for liquid-metal-cooled reactors is currently focused on optimization of the shield design for the Advanced Liquid-Metal-Cooled Reactor reference concept and the performance of a series of integral experiments for the verification of shield design methods. The experimental program, co-sponsored by Japan's Power Reactor and Nuclear Fuel Development Corporation, will extend the previous base of integral data, especially for systems employing boron carbide shielding material. The status of these activities are described and speculation as to future directions and developments are discussed. 3 tabs.
Date: January 1, 1990
Creator: Ingersoll, D.T.
Partner: UNT Libraries Government Documents Department

Structural alloys for high field superconducting magnets

Description: Research toward structural alloys for use in high field superconducting magnets is international in scope, and has three principal objectives: the selection or development of suitable structural alloys for the magnet support structure, the identification of mechanical phenomena and failure modes that may influence service behavior, and the design of suitable testing procedures to provide engineering design data. This paper reviews recent progress toward the first two of these objectives. The structural alloy needs depend on the magnet design and superconductor type and differ between magnets that use monolithic and those that employ force-cooled or ICCS conductors. In the former case the central requirement is for high strength, high toughness, weldable alloys that are used in thick sections for the magnet case. In the latter case the need is for high strength, high toughness alloys that are used in thin welded sections for the conductor conduit. There is productive current research on both alloy types. The service behavior of these alloys is influenced by mechanical phenomena that are peculiar to the magnet environment, including cryogenic fatigue, magnetic effects, and cryogenic creep. The design of appropriate mechanical tests is complicated by the need for testing at 4/sup 0/K and by rate effects associated with adiabatic heating during the tests. 46 refs.
Date: August 1, 1985
Creator: Morris, J.W. Jr.
Partner: UNT Libraries Government Documents Department

TRAC-PF1/MOD1 thermal-hydraulic predictions of JAERI Slab Core Test Facility gravity-feed tests

Description: The Transient Reactor Analysis Code, TRAC-PF1/MOD1, was used to analyze the Slab Core Test Facility gravity-feed tests (Runs 604, 605, 611, and 613) performed by the Japan Atomic Energy Research Institute. The objectives of the TRAC analysis are to compare the TRAC predictions with the test results and to assess the TRAC capability for simulating the core thermal-hydraulic behavior during the reflood phase of a large loss-of-coolant accident. In general, the TRAC-calculated results agree well with the data.
Date: December 1, 1985
Creator: Gilbert, J.S. & Lin, J.C.
Partner: UNT Libraries Government Documents Department

Activities of the PNC Nuclear Safety Working Group

Description: The Nuclear Safety Working Group of the Pacific Nuclear Council promotes nuclear safety cooperation among its members. Status of safety research, emergency planning, development of lists of technical experts, severe accident prevention and mitigation have been the topics of discussion in the NSWG. This paper reviews and compares the severe accident prevention and mitigation program activities in some of the areas of the Pacific Basin region based on papers presented at a special session organized by the NSWG at an ANS Topical Meeting as well as papers from other sources.
Date: January 1, 1991
Creator: Kato, W.Y.
Partner: UNT Libraries Government Documents Department

Reliability of fast reactor mixed-oxide fuel during operational transients

Description: Results are presented from the cooperative DOE and PNC Phase 1 and 2 operational transient testing programs conducted in the EBR-2 reactor. The program includes second (D9 and PNC 316 cladding) and third (FSM, AST and ODS cladding) generation mixed-oxide fuel pins. The irradiation tests include duty cycle operation and extended overpower tests. the results demonstrate the capability of second generation fuel pins to survive a wide range of duty cycle and extended overpower events. 15 refs., 9 figs., 4 tabs.
Date: July 1, 1991
Creator: Boltax, A.; Neimark, L.A.; Tsai, Hanchung (Argonne National Lab., IL (United States)); Katsuragawa, M. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Oarai, Ibaraki (Japan). Oarai Engineering Center)
Partner: UNT Libraries Government Documents Department

Systems work for Plutonium Fuel Production Facility (PFPF) near-real-time accounting

Description: A joint effort by the Los Alamos National Laboratory and the Power Reactor and Nuclear Fuel Development Corporation of Japan examines materials accounting for the Plutonium Fuel Production Facility. A unique feature of the systems work is a sophisticated data generator. This software follows individual items throughout the process, creating detailed data files for variance propagation. The data generator deals with user-specified process operations and handles related accounting problems, such as the tracking of individual measurements through numerous blending and splitting procedure, frequent decay correction (important for large inventories), scrap recovery, and automated determination of static inventory. There is no need to rely on simplified assumptions regarding process operation and material measurement. Also, the joint study applies recent theoretical work on stratified inspection of nonhomogeneous inventories and sequential analysis of MUF -- D. 4 refs.
Date: January 1, 1990
Creator: Picard, R.R.; Hafer, J.F.; Pillay, K.K.S. (Los Alamos National Lab., NM (USA)); Takahashi, S.; Ohtani, T.; Eguchi, K. et al.
Partner: UNT Libraries Government Documents Department

High Burnup Effects Program

Description: This is the final report of the High Burnup Effects Program (HBEP). It has been prepared to present a summary, with conclusions, of the HBEP. The HBEP was an international, group-sponsored research program managed by Battelle, Pacific Northwest Laboratories (BNW). The principal objective of the HBEP was to obtain well-characterized data related to fission gas release (FGR) for light water reactor (LWR) fuel irradiated to high burnup levels. The HBEP was organized into three tasks as follows: Task 1 -- high burnup effects evaluations; Task 2 -- fission gas sampling; and Task 3 -- parameter effects study. During the course of the HBEP, a program that extended over 10 years, 82 fuel rods from a variety of sources were characterized, irradiated, and then examined in detail after irradiation. The study of fission gas release at high burnup levels was the principal objective of the program and it may be concluded that no significant enhancement of fission gas release at high burnup levels was observed for the examined rods. The rim effect, an as yet unquantified contributor to athermal fission gas release, was concluded to be the one truly high-burnup effect. Though burnup enhancement of fission gas release was observed to be low, a full understanding of the rim region and rim effect has not yet emerged and this may be a potential area of further research. 25 refs., 23 figs., 4 tabs.
Date: April 1, 1990
Creator: Barner, J. O.; Cunningham, M. E.; Freshley, M. D. & Lanning, D. D.
Partner: UNT Libraries Government Documents Department

Performance of fast reactor mixed-oxide fuels pins during extended overpower transients

Description: The Operational Reliability Testing (ORT) program, a collaborative effort between the US Department of Energy and the Power Reactor and Nuclear Fuel Development Corp. (PNC) of Japan, was initiated in 1982 to investigate the behavior of mixed-oxide fuel pin under various slow-ramp transient and duty-cycle conditions. In the first phase of the program, a series of four extended overpower transient tests, with severity sufficient to challenge the pin cladding integrity, was conducted. The objectives of the designated TOPI-1A through -1D tests were to establish the cladding breaching threshold and mechanisms, and investigate the thermal and mechanical effects of the transient on pin behavior. The tests were conducted in EBR-2, a normally steady-state reactor. The modes of transient operation in EBR-2 were described in a previous paper. Two ramp rates, 0.1%/s and 10%/s, were selected to provide a comparison of ramp-rate effects on fuel behavior. The test pins chosen for the series covered a range of design and pre-test irradiation parameters. In the first test (1A), all pins maintained their cladding integrity during the 0.1%/s ramp to 60% peak overpower. Fuel pins with aggressive designs, i.e., high fuel- smear density and/or thin cladding, were, therefore, included in the follow-up 1B and 1C tests to enhance the likelihood of achieving cladding breaching. In the meantime, a higher pin overpower capability, to greater than 100%, was established by increasing the reactor power limit from 62.5 to 75 MWt. In this paper, the significant results of the 1B and 1C tests are presented. 4 refs., 5 figs., 1 tab.
Date: February 1, 1991
Creator: Tsai, H.; Neimark, L.A. (Argonne National Lab., IL (USA)); Asaga, T. & Shikakura, S. (Power Reactor and Nuclear Fuel Development Corp., Tokyo (Japan))
Partner: UNT Libraries Government Documents Department

JASPER: A joint US-Japan program of experimental shielding research

Description: A cooperative shielding research program between the US Department of Energy and Japan's Power Reactor and Nuclear Fuel Development Corporation has been initiated. The program includes six specific shielding integral experiments to be performed at the Oak Ridge National Laboratory Tower Shielding Facility and analyzed by both US and Japanese participants. Planned experiments include studies of (1) attenuation in radial shield mockups, (2) neutron streaming in a fission gas plenum, (3) shield effectiveness of different axial shield designs, (4) neutron streaming in narrow gaps, (5) source multiplication effects within in-vessel stored fuel assemblies, and (6) sodium activation in an intermediate heat exchanger mockup. The first experiment, which included numerous configurations containing steel, graphite, and boron carbide, has been completed and initial results are presented. The remaining four experiments, which are in various stages of planning, fabrication and execution, are described briefly.
Date: January 1, 1987
Creator: Ingersoll, D.T. & Ohtani, N.
Partner: UNT Libraries Government Documents Department

Experiments and analysis for an axially heterogeneous LMR assembly at ZPPR

Description: Experiments in ZPPR-17 provided physics data for a full-scale (700 MWe) axially heterogeneous LMR. Measurements and analysis are reported for control rod worths, reaction rate distributions, gamma dose distribution, sodium void worths and criticality. Agreement between measurement and calculation are generally satisfactory, but the axial heterogeneity did introduce analytical complications. Some calculational methods gave less good agreement with measurements than in previous homogeneous or radially heterogeneous assemblies. 10 refs., 7 figs., 6 tabs.
Date: January 1, 1988
Creator: Collins, P.J. & Brumbach, S. B.
Partner: UNT Libraries Government Documents Department

Criticality experiments with mixed oxide fuel pin arrays in plutonium-uranium nitrate solution

Description: A series of critical experiments was completed with mixed plutonium-uranium solutions having a Pu/(Pu + U) ratio of approximately 0.22 in a boiler tube-type lattice assembly. These experiments were conducted as part of the Criticality Data Development Program between the United States Department of Energy (USDOE) and the Power Reactor and Nuclear Fuel Development Corporation (PNC) of Japan. A complete description of the experiments and data are included in this report. The experiments were performed with an array of mixed oxide fuel pins in aqueous plutonium-uranium solutions. The fuel pins were contained in a boiler tube-type tank and arranged in a 1.4 cm square pitch array which resembled cylindrical geometry. One experiment was perfomed with the fuel pins removed from the vessel. The experiments were performed with a water reflector. The concentration of the solutions in the boiler tube-type tank was varied from 4 to 468 g (Pu + U)/liter. The ratio of plutonium to total heavy metal (plutonium plus uranium) was approximately 0.22 for all experiments.
Date: August 1, 1988
Creator: Lloyd, R.C. (Pacific Northwest Lab., Richland, WA (United States)) & Smolen, G.R. (Oak Ridge National Lab., TN (United States))
Partner: UNT Libraries Government Documents Department

(Centralized reliability data organization for liquid metal reactor components)

Description: The Centralized Reliability Data Organization is a data bank and data analysis center, focusing on reliability, availability, and maintainability (RAM) data for components (e.g., valves, pumps, etc.) operating in liquid metal reactors and test facilities. PNC staff are using the CREDO data base as a resource for their development of a probabilistic safety assessment (PSA) for the MONJU fast breeder reactor now under construction. The meeting was held to discuss: (a) progress in FY 1989, (b) resolution of data base deficiencies and inconsistencies, (c) clarification of definitions for failure mode and failure cause, (d) component boundary definitions, (e) goals and objectives for the remainder of the fiscal year, and (f) proposals for future work. General agreement was reached on the need for improvements to the data base: resolution of data deficiencies and inconsistencies, reduction of the number of failure modes and causes, inclusion of failure severity, and a specific delineation of the boundary for each of the generic components. A schedule will be provided to PNC by 1 March 1991 addressing these issues. A proposal to develop a hybrid mainframe/PC reliability data base to improve user access was declined. A second proposal to develop a reliability data base for PNC's nuclear fuel reprocessing facilities was met with a request for more information. A formal proposal will be forwarded to PNC in the near future.
Date: February 7, 1991
Creator: Smith, M.S. & Manneschmidt, J.F.
Partner: UNT Libraries Government Documents Department