- The engineering design of TPX
- The Tokamak Physics Experiment (TPX) is designed to develop the scientific basis for a compact and continuously operating tokamak fusion reactor. TPX has a long pulse (1000s) capability, can accommodate high divertor heat loads, has a flexible PF system, and auxiliary heating and current drive systems that make it an ideal test bed for development ....
- Authors:Reiersen;W.T.Publisher:Fusion Engineering;1993.;15th IEEE/NPSS Symposium onConference Date:11-15 Oct. 1993ISSN:0-7803-1412-3Total Page:2 vol. 1213
- Coil tolerance impact on plasma surface quality for NCSX
- The successful operation of the NCSX machine will require producing plasma configurations with good flux surfaces, with a minimum volume of the plasma lost to magnetic islands or stochastic regions. The project goal is to achieve good flux surfaces over 90 % of the plasma volume. NCSX is a three period device designed to be operated with iota rang....
- Authors:Brooks;A.;Reiersen;W.Publisher:Fusion Engineering;2003. 20th IEEE/NPSS Symposium onConference Date:14-17 Oct. 2003ISSN:0-7803-7908-XTotal Page:xv+651
- Physics optimization of the Compact Ignition Tokamak (CIT)
- The Compact Ignition Tokamak (CIT) is planned as the next major step in the US fusion program. Its overall objective is to produce ignited plasma discharges. In order to realize this objective, plasma parameters which are consistent with recognized theoretical and operational limits and which constitute the most cost-effective path to ignition must....
- Authors:Reiersen;W.T.;Schmidt;J.A.;Montgomery;D.B.Publisher:Fusion Engineering;1989. Proceedings.;IEEE Thirteenth Symposium onConference Date:2-6 Oct. 1989ISSN:Total Page:2 vol. 1569
- Neutral beam injection requirements and design issues for the National Compact Stellarator Experiment
- NCSX will require 6 MW of 50 keV neutral beam injection with initial pulse lengths of 500 msec and upgradeable to pulse lengths of 1.5 sec. This paper discusses the NCSX NBI requirements and design issues, and shows how these are provided by the candidate PBX-M NBI system.
- Authors:Kugel;H.W.;Neilson;H.;Reiersen;W.;Zarnstorff;M.;Cole;M.Publisher:Fusion Engineering;2002. 19th Symposium onConference Date:21-25 Jan. 2002ISSN:0-7803-7073-2Total Page:xii+497
- The experimental evaluation of the success path monitoring system
- The success path monitoring system (SPMS) is an advanced computer-based operator aid which is intended to enhance the operator's ability to handle plant disturbances effectively. It achieves this by providing an online assessment of both the status of critical safety functions and the status of appropriate success paths. A prototype version of SPMS....
- Authors:Marshall;E.C.;Baker;S.M.;Reiersen;C.S.;Owre;F.;Gaudio;P.J.;Jr.Publisher:Human Factors and Power Plants;1988.;Conference Record for 1988 IEEE Fourth Conference onConference Date:5-9 June 1988ISSN:Total Page:xii+596
- Physics design requirements for the Tokamak Physics Experiment (TPX)
- The design of TPX is driven by physics requirements that follow from its mission. The tokamak and heating systems provide the performance and profile controls needed to study advanced steady state tokamak operating modes. The magnetic control systems provide substantial flexibility for the study of regimes with high beta and bootstrap current. The ....
- Authors:Neilson;G.;Goldston;R.;Jardin;S.C.;Nevins;W.;Porkolab;M.;Reiersen;W.;Ulrickson;M.Publisher:Fusion Engineering;1993.;15th IEEE/NPSS Symposium onConference Date:11-15 Oct. 1993ISSN:0-7803-1412-3Total Page:2 vol. 1213
- A comparative assessment of centerpost design options for ARIES-ST
- The ARIES team is presently assessing the feasibility of a low aspect ratio (LAR) or spherical tokamak (ST) to serve as a commercial power plant. Development of a credible design for the centerpost is one of the key feasibility issues. In this paper, centerpost design options are identified and systematically assessed.
- Authors:Reiersen;W.;Dahlgren;F.;Steiner;D.;Bonanos;P.;Bromberg;L.;Neumeyer;C.;Fan;H.Publisher:Fusion Engineering;1997. 17th IEEE/NPSS SymposiumConference Date:6-10 Oct. 1997ISSN:0-7803-4226-7Total Page:2 vol. xxiv+1156
- NCSX electrical power systems
- The National Compact Stellarator Experiment (NCSX) is being designed to be built in the existing facilities at Princeton Plasma Physics Laboratory (PPPL). The design of the NCSX electrical power system is tailored to suit the available infrastructure and electrical equipment on site. The equipment at PPPL is located primarily in two sites called C-....
- Authors:Ramakrishnan;S.;Neumeyer;C.;Hatcher;R.;Marsala;R.;Baker;E.;Schneider;H.;Reiersen;W.Publisher:Fusion Engineering;2002. 19th Symposium onConference Date:21-25 Jan. 2002ISSN:0-7803-7073-2Total Page:xii+497
- Conceptual design of KSTAR vacuum vessel
- The Korea Superconducting Tokamak Advanced Research (KSTAR) is a steady-state-capable superconducting tokamak. The vacuum vessel (VV) system consists of the toroidal vessel inner and outer shells, radial, horizontal and vertical ports, vessel supports, plasma facing components (PFCs) and their supports. The vessel is a double wall design with inner....
- Authors:Cho;S.;Yoon;B.J.;Kim;J.;Brown;T.G.;Dahlgren;F.;In;S.R.;Kim;H.S.;Lee;G.S.;Park;H.K.;Reiersen;W.Publisher:Fusion Engineering;1997. 17th IEEE/NPSS SymposiumConference Date:6-10 Oct. 1997ISSN:0-7803-4226-7Total Page:2 vol. xxiv+1156
- The KSTAR superconducting magnet system
- The Korean Superconducting Tokamak Advanced Research (KSTAR) at the Korea Basic Science Institute in Taejon will be the first Tokamak with an advanced all superconducting magnet system, including toroidal field (TF), poloidal field (PF),and field error correction (FEC) coils. The conductors are all cable-in-conduit (CICC) superconductors with a sin....
- Authors:Schultz;J.H.;Michel;P.;Myatt;L.M.;Radovinsky;A.;Wang;P.W.;Reiersen;W.;Brown;T.;Kim;K.;Baang;S.;Choi;H.Publisher:Fusion Engineering;1997. 17th IEEE/NPSS SymposiumConference Date:6-10 Oct. 1997ISSN:0-7803-4226-7Total Page:2 vol. xxiv+1156
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