Search Results - "MERRILL, B. J"

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  1. 1

    Tcf3 and Lef1 regulate lineage differentiation of multipotent stem cells in skin by Merrill, B J, Gat, U, DasGupta, R, Fuchs, E

    Published in Genes & development (01-07-2001)
    “…In skin, multipotent stem cells generate the keratinocytes of the epidermis, sebaceous gland, and hair follicles. In this paper, we show that Tcf3 and Lef1…”
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    Journal Article
  2. 2

    Development of positron annihilation spectroscopy for characterizing neutron irradiated tungsten by Taylor, C N, Shimada, M, Merrill, B J, Drigert, M W, Akers, D W, Hatano, Y

    Published in Physica scripta (01-04-2014)
    “…Tungsten samples (6 mm diameter and 0.2 mm thick) were irradiated to 0.025 and 0.3 dpa with neutrons in the High Flux Isotope Reactor at Oak Ridge National…”
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    Journal Article
  3. 3

    An overview of the US DCLL ITER-TBM program by Wong, C.P.C., Abdou, M., Dagher, M., Katoh, Y., Kurtz, R.J., Malang, S., Marriott, E.P., Merrill, B.J., Messadek, K., Morley, N.B., Sawan, M.E., Sharafat, S., Smolentsev, S., Sze, D.K., Willms, S., Ying, A., Youssef, M.Z.

    Published in Fusion engineering and design (01-12-2010)
    “…Under the US Fusion Nuclear Science and Technology program, we selected the Dual Coolant Lead Lithium (DCLL) concept as our primary Test Blanket Module (TBM)…”
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    Journal Article Conference Proceeding
  4. 4

    Modifications to the MELCOR code for application in fusion accident analyses by Merrill, B.J, Moore, R.L, Polkinghorne, S.T, Petti, D.A

    Published in Fusion engineering and design (01-11-2000)
    “…For the past several years, the Fusion Safety Program at the Idaho National Engineering and Environmental Laboratory (INEEL) has modified the MELCOR code in…”
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    Journal Article Conference Proceeding
  5. 5

    ARIES-AT safety design and analysis by Petti, D.A., Merrill, B.J., Moore, R.L., Longhurst, G.R., El-Guebaly, L., Mogahed, E., Henderson, D., Wilson, P., Abdou, A.

    Published in Fusion engineering and design (2006)
    “…ARIES-AT is a 1000 MWe conceptual fusion power plant design with a very low projected cost of electricity. The design contains many innovative features to…”
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    Journal Article
  6. 6

    Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten by Taylor, C.N., Shimada, M., Merrill, B.J., Akers, D.W., Hatano, Y.

    Published in Journal of nuclear materials (01-08-2015)
    “…The present work is a continuation of a recent research to develop and optimize positron annihilation spectroscopy (PAS) for characterizing neutron-irradiated…”
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    Journal Article
  7. 7

    A fusion reactor design with a liquid first wall and divertor by Nygren, R.E., Rognlien, T.D., Rensink, M.E., Smolentsev, S.S., Youssef, M.Z., Sawan, M.E., Merrill, B.J., Eberle, C., Fogarty, P.J., Nelson, B.E., Sze, D.K., Majeski, R.

    Published in Fusion engineering and design (01-11-2004)
    “…Within the magnetic fusion energy program in the US, a program called APEX is investigating the use of free flowing liquid surfaces to form the inner surface…”
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    Journal Article
  8. 8

    A revised and expanded liquid metal property library for MELCOR by Humrickhouse, P.W., Merrill, B.J.

    Published in Fusion engineering and design (01-09-2019)
    “…The liquid metal thermophysical properties library in MELCOR for Fusion has been comprehensively revised. In addition to the existing liquid metals Li, Na, and…”
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    Journal Article
  9. 9

    Deuterium/tritium behavior in Flibe and Flibe-facing materials by Anderl, R.A, Fukada, S, Smolik, G.R, Pawelko, R.J, Schuetz, S.T, Sharpe, J.P, Merrill, B.J, Petti, D.A, Nishimura, H, Terai, T, Tanaka, S

    Published in Journal of nuclear materials (01-08-2004)
    “…Experimental studies to investigate the behavior of deuterium and tritium in the molten salt Flibe (2LiF · BeF 2), have been conducted as part of the Japan–US…”
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    Journal Article
  10. 10

    Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO by Merrill, B.J., Wong, C.P.C., Cadwallader, L.C., Abdou, M., Morley, N.B.

    Published in Fusion engineering and design (01-10-2014)
    “…A leading power reactor breeding blanket candidate for a fusion demonstration power plant (DEMO) being pursued by the US Fusion Community is the Dual Coolant…”
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    Journal Article
  11. 11

    Modifications to the MELCOR-TMAP code to simultaneously treat multiple fusion coolants by Merrill, B.J., Humrickhouse, P.W., Yoon, S-J.

    Published in Fusion engineering and design (01-09-2019)
    “…•Different working fluids per given coolant system.•Coupled hydrogen isotope transport in Henry’s Law fluids and Sieverts’ Law materials.•Benchmarking of these…”
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    Journal Article
  12. 12

    Safety assessment of two advanced ferritic steel molten salt blanket design concepts by Merrill, B.J., Sawan, M., Wong, C.P.C., Nygren, R.E., Cadwallader, L.C., Malang, S., Sze, D.-K.

    Published in Fusion engineering and design (01-11-2004)
    “…In this article, we explore some of the safety issues associated with two advanced ferritic steel (AFS) molten salt blanket designs from the Advanced Power…”
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    Journal Article
  13. 13

    At the Roots of a Never-Ending Cycle by Fuchs, Elaine, Merrill, Bradley J., Jamora, Colin, DasGupta, Ramanuj

    Published in Developmental Cell (01-07-2001)
    “…Recent studies have yielded a number of important insights into the mechanisms of hair follicle development and cycling and have highlighted the particularly…”
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    Book Review Journal Article
  14. 14

    Oxygen reactivity of a carbon fiber composite by Marshall, T.D, Pawelko, R.J, Anderl, R.A, Smolik, G.R, Merrill, B.J, Moore, R.L, Petti, D.A

    Published in Fusion engineering and design (01-09-2003)
    “…Carbon Fiber Composites (CFCs) are often suggested as armor material for the first wall of a fusion plasma chamber due to carbon's low atomic number, high…”
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    Journal Article Conference Proceeding
  15. 15

    Safety implications of CLiFF liquid metal first walls by Merrill, B.J, Sze, D.-K, Khater, H.Y, Mogahed, E.A

    Published in Fusion engineering and design (01-12-2002)
    “…In this article we explore some of the safety issues associated with the Advanced Power Extraction (APEX) liquid metal first wall (FW) concept called the…”
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    Journal Article Conference Proceeding
  16. 16

    Tcf3: a transcriptional regulator of axis induction in the early embryo by Merrill, Bradley J, Pasolli, H Amalia, Polak, Lisa, Rendl, Michael, García-García, Maria J, Anderson, Kathryn V, Fuchs, Elaine

    Published in Development (Cambridge) (15-01-2004)
    “…The roles of Lef/Tcf proteins in determining cell fate characteristics have been described in many contexts during vertebrate embryogenesis, organ and tissue…”
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    Journal Article
  17. 17

    Safety issues associated with mobilized activation products in selected APEX designs by McCarthy, K.A, Petti, D.A, Moore, R.L, Merrill, B.J

    Published in Fusion engineering and design (01-11-2000)
    “…In the advanced power extraction (APEX) project, safety and environmental concerns considered up front, as designs evolve, so that the goal of safety and…”
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    Journal Article Conference Proceeding
  18. 18

    Wnt pathway regulation of embryonic stem cell self-renewal by Merrill, Bradley J

    Published in Cold Spring Harbor perspectives in biology (01-09-2012)
    “…Embryonic stem cells (ESCs) can generate all of the cell types found in the adult organism. Remarkably, they retain this ability even after many cell divisions…”
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    Journal Article
  19. 19

    Safety analysis results for ITER in-vessel loss of coolant events by PETTI, D. A, MERRILL, B. J, POLKINGHORNE, S. T, CADWALLADER, L. C, MOORE, R. L

    Published in Journal of fusion energy (01-06-1997)
    “…A number of postulated in-vessel loss of coolant accidents (LOCAs) associated with the first wall and baffle cooling systems of the ITER detailed design have…”
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    Conference Proceeding Journal Article
  20. 20

    Safety analysis results for cryostat ingress accidents in ITER by MERRILL, B. J, CADWALLADER, L. C, PETTI, D. A

    Published in Journal of fusion energy (01-06-1997)
    “…Accidents involving the ingress of air, helium, or water into the cryostat of the International Thermonuclear Experimental Reactor (ITER) tokamak design have…”
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    Conference Proceeding Journal Article