Search Results - "MERRILL, B. J"
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Tcf3 and Lef1 regulate lineage differentiation of multipotent stem cells in skin
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
Development of positron annihilation spectroscopy for characterizing neutron irradiated tungsten
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
An overview of the US DCLL ITER-TBM program
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
Modifications to the MELCOR code for application in fusion accident analyses
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
ARIES-AT safety design and analysis
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
Development of positron annihilation spectroscopy for investigating deuterium decorated voids in neutron-irradiated tungsten
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
A fusion reactor design with a liquid first wall and divertor
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
A revised and expanded liquid metal property library for MELCOR
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
Deuterium/tritium behavior in Flibe and Flibe-facing materials
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
Normal operation and maintenance safety lessons from the ITER US PbLi test blanket module program for a US FNSF and DEMO
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 -
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Modifications to the MELCOR-TMAP code to simultaneously treat multiple fusion coolants
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 -
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Safety assessment of two advanced ferritic steel molten salt blanket design concepts
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
At the Roots of a Never-Ending Cycle
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
Oxygen reactivity of a carbon fiber composite
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
Safety implications of CLiFF liquid metal first walls
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
Tcf3: a transcriptional regulator of axis induction in the early embryo
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 -
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Safety issues associated with mobilized activation products in selected APEX designs
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
Wnt pathway regulation of embryonic stem cell self-renewal
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 -
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Safety analysis results for ITER in-vessel loss of coolant events
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
Safety analysis results for cryostat ingress accidents in ITER
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