Countries citing papers authored by R.D. Cheverton
Since
Specialization
Citations
This map shows the geographic impact of R.D. Cheverton'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 R.D. Cheverton with the expected number of citations based on a country's size and research output (numbers larger than one mean the country cites R.D. Cheverton more than expected).
This network shows the impact of papers produced by R.D. Cheverton. 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 R.D. Cheverton. The network helps show where R.D. Cheverton may publish in the future.
Co-authorship network of co-authors of R.D. Cheverton
This figure shows the co-authorship network connecting the top 25 collaborators of R.D. Cheverton.
A scholar is included among the top collaborators of R.D. Cheverton 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 R.D. Cheverton. R.D. Cheverton 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.
Cheverton, R.D.. (1993). Large-scale thermal-shock experiments with clad and unclad steel cylinders.1 indexed citations
Cheverton, R.D., et al.. (1992). Review of reactor pressure vessel evaluation report for Yankee Rowe Nuclear Power Station (YAEC No. 1735). OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).2 indexed citations
Cheverton, R.D., et al.. (1985). Pressure vessel fracture studies pertaining to the PWR thermal-shock issue: experiment TSE-7. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).7 indexed citations
9.
Cheverton, R.D., et al.. (1984). OCA-P, a deterministic and probabilistic fracture-mechanics code for application to pressure vessels. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).22 indexed citations
Cheverton, R.D., et al.. (1983). PWR pressure vessel integrity during overcooling accidents: a parametric analysis. University of North Texas Digital Library (University of North Texas).4 indexed citations
12.
Cheverton, R.D., et al.. (1983). Modification of OCA-I for application to a reactor pressure vessel with cladding on the inner surface. [PWR].2 indexed citations
13.
Cheverton, R.D., et al.. (1982). Fracture mechanics data deduced from thermal-shock snd related experiments with LWR pressure vessel material.. 58. 1–16.4 indexed citations
14.
Cheverton, R.D., et al.. (1982). Integrity of PWR pressure vessels during overcooling accidents. University of North Texas Digital Library (University of North Texas). 41.2 indexed citations
Iskander, S.K., et al.. (1981). OCA-I, a code for calculating the behavior of flaws on the inner surface of a pressure vessel subjected to temperature and pressure transients. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).3 indexed citations
17.
Cheverton, R.D., et al.. (1981). Experimental verification of the behavior of surface flaws in thick-walled steel cylinders during severe thermal shock. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).5 indexed citations
18.
Cheverton, R.D.. (1978). Thermal shock studies associated with injection of emergency core coolant following a loss-of-coolant accident in PWRs.2 indexed citations
19.
Swartout, Jeff, et al.. (1964). THE OAK RIDGE HIGH FLUX ISOTOPE REACTOR. OSTI OAI (U.S. Department of Energy Office of Scientific and Technical Information).
20.
Cheverton, R.D.. (1959). HIGH FLUX ISOTOPE REACTOR. Nuclear Science and Engineering.1 indexed citations
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