This map shows the geographic impact of W.N. McElroy's research. It shows the number of citations coming from papers published by authors working in each country. You can also color the map by specialization and compare the number of citations received by W.N. McElroy with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites W.N. McElroy more than expected).
This network shows the impact of papers produced by W.N. McElroy. Nodes represent research fields, and links connect fields that are likely to share authors. Colored nodes show fields that tend to cite the papers produced by W.N. McElroy. The network helps show where W.N. McElroy may publish in the future.
Co-authorship network of co-authors of W.N. McElroy
This figure shows the co-authorship network connecting the top 25 collaborators of W.N. McElroy.
A scholar is included among the top collaborators of W.N. McElroy based on the total number of
citations received by their joint publications. Widths of edges
represent the number of papers authors have co-authored together.
Node borders
signify the number of papers an author published with W.N. McElroy. W.N. McElroy is excluded from
the visualization to improve readability, since they are connected to all nodes in the network.
All Works
20 of 20 papers shown
1.
Gold, R., et al.. (1983). Fuel debris assessment for Three Mile Island Unit 2 (TMI-2) reactor recovery by gamma-ray and neutron dosimetry. University of North Texas Digital Library (University of North Texas).
2.
Guthrie, G.L. & W.N. McElroy. (1983). LWR pressure vessel surveillance dosimetry improvement program. Quarterly progress report, January 1982-March 1982. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).
3.
Gold, R., W.N. McElroy, E.P. Lippincott, et al.. (1980). Cross sections required for FMIT dosimetry. University of North Texas Digital Library (University of North Texas).1 indexed citations
4.
Gold, R., et al.. (1979). Neutron dosimetry characterization of spent thermal reactor fuel assemblies. Transactions of the American Nuclear Society. 32.2 indexed citations
5.
McElroy, W.N., et al.. (1977). FFTF reactor characterization program. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information). 39.1 indexed citations
6.
Lippincott, E.P., et al.. (1975). Helium production in reactor materials. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information). 1.
McElroy, W.N., et al.. (1974). Reaction rate measurements in CFRMF. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).1 indexed citations
10.
Odette, G.R., Robert L. Simons, & W.N. McElroy. (1974). Reactor materials performance predictions: a critique of damage functions analysis. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).1 indexed citations
11.
Gold, R. & W.N. McElroy. (1974). Critical requirements of the SSTR method. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).1 indexed citations
12.
McElroy, W.N., et al.. (1972). DAMAGE FUNCTION FOR SWELLING IN TYPE 304 STAINLESS STEEL.. Transactions of the American Nuclear Society.1 indexed citations
McElroy, W.N., et al.. (1969). DAMAGE-FUNCTION ANALYSIS OF NEUTRON-ENERGY AND SPECTRUM EFFECTS UPON THE RADIATION EMBRITTLEMENT OF STEELS.. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).6 indexed citations
16.
McElroy, W.N., et al.. (1968). NEUTRON DIFFERENTIAL CROSS-SECTION EVALUATION BY A MULTIPLE FOIL ACTIVATION ITERATIVE METHOD.. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information). 235.1 indexed citations
McElroy, W.N., et al.. (1967). A COMPUTER-AUTOMATED ITERATIVE METHOD FOR NEUTRON FLUX SPECTRA DETERMINATION BY FOIL ACTIVATION. Technical Report, April 1966--July 1967.. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).2 indexed citations
19.
McElroy, W.N., et al.. (1967). A COMPUTER-AUTOMATED ITERATIVE METHOD FOR NEUTRON FLUX SPECTRA DETERMINATION BY FOIL ACTIVATION. VOLUME 1. A STUDY OF THE ITERATIVE METHOD. Defense Technical Information Center (DTIC).41 indexed citations
20.
Hetrick, D.L., et al.. (1953). Experimental Determination of the Effect of Reactor Radiation on the Thermal Conductivity of Uranium-Impregnated Graphite. University of North Texas Digital Library (University of North Texas).2 indexed citations
Rankless uses publication and citation data sourced from OpenAlex, an open and comprehensive
bibliographic database. While OpenAlex provides broad and valuable coverage of the global
research landscape, it—like all bibliographic datasets—has inherent limitations. These include
incomplete records, variations in author disambiguation, differences in journal indexing, and
delays in data updates. As a result, some metrics and network relationships displayed in
Rankless may not fully capture the entirety of a scholar's output or impact.