Search Results - "Mattas, R.F"

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  1. 1

    Results of R&D for lithium/vanadium breeding blanket design by Mattas, R.F, Smith, D.L, Reed, C.B, Park, J.H, Kirillov, I.R, Strebkov, Yu.S, Rusanov, A.E, Votinov, S.N

    Published in Fusion engineering and design (01-09-1998)
    “…The self-cooled lithium/vanadium blanket concept has several attractive features for fusion power systems, including reduced activation, resistance to…”
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    Journal Article
  2. 2

    ALPS–advanced limiter-divertor plasma-facing systems by Mattas, R.F, Allain, J.P, Bastasz, R, Brooks, J.N, Evans, T, Hassanein, A, Luckhardt, S, McCarthy, K, Mioduszewski, P, Maingi, R, Mogahed, E, Moir, R, Molokov, S, Morely, N, Nygren, R, Rognlien, T, Reed, C, Ruzic, D, Sviatoslavsky, I, Sze, D, Tillack, M, Ulrickson, M, Wade, P.M, Wooley, R, Wong, C

    Published in Fusion engineering and design (01-11-2000)
    “…The advanced limiter-divertor plasma-facing systems (ALPS) program was initiated in order to evaluate the potential for improved performance and lifetime for…”
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    Journal Article Conference Proceeding
  3. 3

    Development of electrically insulating coatings on vanadium alloys for lithium-cooled blankets by Smith, D.L, Natesan, K, Park, J.-H, Reed, C.B, Mattas, R.F

    Published in Fusion engineering and design (01-11-2000)
    “…The self-cooled lithium blanket concept with a vanadium structure offers a potential for high performance with attractive safety and environmental features…”
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    Journal Article Conference Proceeding
  4. 4

    Materials integration issues for high performance fusion power systems by Smith, D.L, Billone, M.C, Majumdar, S, Mattas, R.F, Sze, D.-K

    Published in Journal of nuclear materials (01-10-1998)
    “…One of the primary requirements for the development of fusion as an energy source is the qualification of materials for the first-wall/blanket system that will…”
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    Journal Article
  5. 5

    Materials for breeding blankets by Mattas, R.F., Billone, M.C.

    Published in Journal of nuclear materials (01-10-1996)
    “…There are several candidate concepts for tritium breeding blankets that make use of a number of special materials. These materials can be classified as primary…”
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    Journal Article
  6. 6

    Liquid lithium self-cooled breeding blanket design for ITER by Kirillov, I.R, Danilov, I.V, Sidorenkov, S.I, Strebkov, Yu.S, Mattas, R.F, Gohar, Y, Hua, T.Q, Smith, D.L

    Published in Fusion engineering and design (01-09-1998)
    “…To meet the technical objectives of the ITER extended performance phase (EPP) an advanced tritium breeding lithium/vanadium (Li/V) blanket was developed by two…”
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    Journal Article
  7. 7

    Assessment of alkali metal coolants for the ITER blanket by Natesan, K, Reed, C.B, Mattas, R.F

    Published in Fusion engineering and design (01-03-1995)
    “…The blanket system is one of the most important components of a fusion reactor becuase it has a major impact on both the economics and safety of fusion energy…”
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    Journal Article
  8. 8

    EVOLVE—an advanced first wall/blanket system by Mattas, R.F., Malang, S., Khater, H., Majumdar, S., Mogahed, E., Nelson, B., Sawan, M., Sze, D.K.

    Published in Fusion engineering and design (01-11-2000)
    “…A new concept for an advanced fusion first wall and blanket has been identified. The key feature of the concept is the use of the heat of vaporization of…”
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    Journal Article Conference Proceeding
  9. 9

    Vanadium alloys for fusion reactor applications by Mattas, R. F., Loomis, B. A., Smith, D. L.

    Published in JOM (1989) (01-08-1992)
    “…Fusion reactors will produce a severe operating environment for structural materials. The material should have good mechanical strength and ductility to high…”
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    Journal Article
  10. 10

    Measurement techniques for fusion blanket neutronics experiments by Oyama, Y, Konno, C, Ikeda, Y, Maekawa, F, Maekawa, H, Yamaguchi, S, Tsuda, K, Nakamura, T, Abdou, M.A, Bennett, E.F, Mattas, R.F, Porges, K.G, Youssef, M.Z

    Published in Fusion engineering and design (01-03-1995)
    “…A variety of techniques to measure the nuclear parameters, such as tritium production rate, neutron spectrum, reaction rate and gamma-ray heating, in a…”
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    Journal Article
  11. 11

    Plasma–materials interaction issues for the International Thermonuclear Experimental Reactor (ITER) by Cohen, S. A., Mattas, R. F., Werley, K. A.

    “…At the extreme conditions expected for some operating scenarios of the International Thermonuclear Experimental Reactor, commonly used heat‐removal structures…”
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    Conference Proceeding Journal Article