scholarly journals Characteristics of potential repository wastes: Volume 4, Appendix 4A, Nuclear reactors at educational institutions of the United States; Appendix 4B, Data sheets for nuclear reactors at educational institutions; Appendix 4C, Supplemental data for Fort St. Vrain spent fuel; Appendix 4D, Supplemental data for Peach Bottom 1 spent fuel; Appendix 4E, Supplemental data for Fast Flux Test Facility

1992 ◽  
Author(s):  
2015 ◽  
Vol 4 (1) ◽  
Author(s):  
Siluvai Raja

Education has been considered as an indispensable asset of every individual, community and nation today. Indias higher education system is the third largest in the world, after China and the United States (World Bank). Tamil Nadu occupies the first place in terms of possession of higher educational institutions in the private sector in the country with over 46 percent(27) universities, 94 percent(464) professional colleges and 65 percent(383) arts and science colleges(2011). Studies to understand the profile of the entrepreneurs providing higher education either in India or Tamil Nadu were hardly available. This paper attempts to map the demographic profile of the entrepreneurs providing higher education in Arts and Science colleges in Tamil Nadu through an empirical analysis, carried out among 25 entrepreneurs spread across the state. This paper presents a summary of major inferences of the analysis.


MRS Advances ◽  
2018 ◽  
Vol 3 (19) ◽  
pp. 991-1003 ◽  
Author(s):  
Evaristo J. Bonano ◽  
Elena A. Kalinina ◽  
Peter N. Swift

ABSTRACTCurrent practice for commercial spent nuclear fuel management in the United States of America (US) includes storage of spent fuel in both pools and dry storage cask systems at nuclear power plants. Most storage pools are filled to their operational capacity, and management of the approximately 2,200 metric tons of spent fuel newly discharged each year requires transferring older and cooler fuel from pools into dry storage. In the absence of a repository that can accept spent fuel for permanent disposal, projections indicate that the US will have approximately 134,000 metric tons of spent fuel in dry storage by mid-century when the last plants in the current reactor fleet are decommissioned. Current designs for storage systems rely on large dual-purpose (storage and transportation) canisters that are not optimized for disposal. Various options exist in the US for improving integration of management practices across the entire back end of the nuclear fuel cycle.


Science ◽  
2021 ◽  
Vol 372 (6538) ◽  
pp. eabg3055 ◽  
Author(s):  
Nicholas G. Davies ◽  
Sam Abbott ◽  
Rosanna C. Barnard ◽  
Christopher I. Jarvis ◽  
Adam J. Kucharski ◽  
...  

A severe acute respiratory syndrome coronavirus 2 (SARS-CoV-2) variant, VOC 202012/01 (lineage B.1.1.7), emerged in southeast England in September 2020 and is rapidly spreading toward fixation. Using a variety of statistical and dynamic modeling approaches, we estimate that this variant has a 43 to 90% (range of 95% credible intervals, 38 to 130%) higher reproduction number than preexisting variants. A fitted two-strain dynamic transmission model shows that VOC 202012/01 will lead to large resurgences of COVID-19 cases. Without stringent control measures, including limited closure of educational institutions and a greatly accelerated vaccine rollout, COVID-19 hospitalizations and deaths across England in the first 6 months of 2021 were projected to exceed those in 2020. VOC 202012/01 has spread globally and exhibits a similar transmission increase (59 to 74%) in Denmark, Switzerland, and the United States.


1981 ◽  
Vol 11 ◽  
Author(s):  
H. C. Burkholder

In response to draft radioactive waste disposal standards, R&D programs have been initiated in the United States which are aimed at developing and ultimately using radionuclide transport-delaying (e.g., long-lived waste containers) and radionuclide transport-controlling (e.g., very low release rate waste forms) engineered components as part of the isolation system. Before these programs proceed significantly, it seems prudent to evaluate the technical justification for development and use of sophisticated engineered components in radioactive waste isolation.


Author(s):  
G. B. Manning

The design of the first compact AK Process Nuclear system in the United States was performed under the auspices of the Corps of Engineers. U. S. Army, Fort Belvoir, Va. Taking into account that there was virtually nothing on the shelf that could be used, and realizing that the feasibility of such a system first had to be established, demonstration models were built for the various subsystem components which were to eventually go into the complete system. The last and final turbine-compressor set tested as a backup unit for this program was the TCS 670-B. This paper reports the turbine performance obtained from this machine when tested in the Closed Cycle Test Facility (APCEF) at Fort Belvoir, Va.. in 1969. The compressor performance is not included.


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