Zobrazeno 1 - 10
of 248
pro vyhledávání: '"V. M. Oversby"'
Autor:
P. Henderson
Publikováno v:
Mineralogical Magazine. 39:258-259
Autor:
V. M. Oversby
Publikováno v:
Materials Science and Technology ISBN: 9783527603978
Materials Science and Technology
Materials Science and Technology
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::a360d1e820941759004b07f748fc3fc6
https://doi.org/10.1002/9783527603978.mst0116
https://doi.org/10.1002/9783527603978.mst0116
Autor:
V. M. Oversby, M. K. Silva
Publikováno v:
MRS Proceedings. 663
The Waste Isolation Pilot Plant (WIPP) is located at a depth of 655 m in bedded salt at a site about 40 km east of Carlsbad, New Mexico.The 1996 U. S. Department of Energy (DOE) application for certification by the U. S. Environmental Protection Agen
Autor:
V. M. Oversby
Publikováno v:
MRS Proceedings. 556
In the early 1980s, tests of the leaching behavior of spent light water reactor fuel were conducted in Sweden by SKB and in the USA by the NNWSI Project. Both organizations used fuels with similar burnup, leaching solutions with similar chemical comp
Autor:
V. M. Oversby
Publikováno v:
MRS Proceedings. 608
The Oklo Natural Analogue Project, Phase II was conducted by an international consortium of researchers under the sponsorship of the European Union. An important objective of the project was to examine the potential for extracting quantitative inform
Autor:
V. M. Oversby
Publikováno v:
Actinides and the Environment ISBN: 9789048150021
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::859dab8a7b39a4291704c95c499088d4
https://doi.org/10.1007/978-94-017-0615-5_16
https://doi.org/10.1007/978-94-017-0615-5_16
Autor:
V. M. Oversby
Publikováno v:
MRS Proceedings. 506
The conditions that are needed to achieve criticality in a high level waste repository for spent nuclear reactor fuel are reviewed. The effect of initial enrichment of the fuel, burnup, and of mixed oxide fuels on the conditions for criticality are d
Autor:
J. Weir, Eric R. Vance, E. Loi, Bruce D. Begg, P. J. Angel, V. M. Oversby, K. P. Hart, R. A. Day
Publikováno v:
MRS Proceedings. 412
A titanate Synroc ceramic for the immobilization of Pu-bearing waste was designed to consist of 70 wt% zirconolite (CaZrTi2O7) + 15 wt% nepheline (NaAlSiO4) + 15 wt% rutile (TiO2). It contained 10 wt% of Pu plus 6 wt% of Gd as a neutron poison. The m
Publikováno v:
MRS Proceedings. 353
The immobilisation of excess weapons plutonium into Synroc can meet all of the important criteria discussed by the U.S. National Academy of Sciences (NAS)(1)for disposal, if the disposal option is pursued rather than options that exploit the energy v