Zobrazeno 1 - 10
of 22
pro vyhledávání: '"D.B. Lancaster"'
Autor:
Teruhiko Kugo, Giuseppe Palmiotti, Edward (Fitz) Trumble, D.B. Lancaster, J. Blair Briggs, Albert C. Kahler
Publikováno v:
Nuclear Science and Engineering. 178:295-310
The International Reactor Physics Experiment Evaluation Project (IRPhEP) and the International Criticality Safety Benchmark Evaluation Project (ICSBEP) provide evaluated integral benchmark data that may be used for validation of reactor physics / nuc
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::fc44889abc9e63cebad8d0edc0be8996
https://doi.org/10.13182/nse14-33
https://doi.org/10.13182/nse14-33
Publikováno v:
Nuclear Technology. 185:39-56
Pressurized water reactor (PWR) assembly reactivity distributions are inferred from ~600 in-core flux maps taken during 44 cycles of operation of the Catawba and McGuire nuclear power plants. The r...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::3080eb3602af3f74ebc31a0382d42cb3
https://doi.org/10.13182/nt13-31
https://doi.org/10.13182/nt13-31
Publikováno v:
Nuclear Technology. 185:57-70
The Electric Power Research Institute (EPRI) has sponsored the development of a set of benchmarks that can be used to quantify the bias and uncertainty in computed reactivity decrements due to burn...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::2d6dfbb904334a5c8f5d88bf99186883
https://doi.org/10.13182/nt13-28
https://doi.org/10.13182/nt13-28
Autor:
L Stewart, W Bishop, Craig F. Smith, J Herezeg, T Cotton, William G. Halsey, E Schweitzer, H. Ludewig, Denis Beller, Phillip J. Finck, J.S Herring, G. Van Tuyle, T Sanders, D.B. Lancaster, Jose March-Leuba, Michael Todosow, B Savage, C.E. Walter, David L. Hill
Publikováno v:
Progress in Nuclear Energy. 38:3-23
A roadmap has been established for development of ATW Technology. The roadmap defines a reference system along with preferred technologies, which require further development to reduce technical risk, associated deployment scenarios, and a detailed pl
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::655f2a13bf332e4fd4161173a05f134b
https://doi.org/10.1016/s0149-1970(00)00094-9
https://doi.org/10.1016/s0149-1970(00)00094-9
Actinide-Only Burnup Credit for Pressurized Water Reactor Spent Nuclear Fuel—I: Methodology Overview
Publikováno v:
Nuclear Technology. 125:255-270
A conservative methodology is presented that would allow taking credit for burnup in the criticality safety analysis of spent nuclear fuel (SNF) packages. The method is based on the assumption that the isotopic concentration in the SNF and cross sect
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::55e7fd31d2bed288104ab6ed5b7f5cd1
https://doi.org/10.13182/nt99-a2946
https://doi.org/10.13182/nt99-a2946
Autor:
D.B. Lancaster, Chi H. Kang
Publikováno v:
Nuclear Technology. 125:292-304
A flat, uniform axial burnup assumption, preferred for its computational simplicity, does not always conservatively estimate the pressurized water reactor spent-fuel-cask multiplication factors. Rather, the reactivity effect of the significantly unde
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1105c825800448808bdf3f86306d86d8
https://doi.org/10.13182/nt99-a2948
https://doi.org/10.13182/nt99-a2948
Publikováno v:
Nuclear Technology. 125:271-291
The calculation of isotopic concentrations in spent nuclear fuel (SNF) assemblies and the subcritical multiplication factor of SNF packages are two of the essential requirements of the actinide-only burnup credit methodology. To justify the accuracy
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::1e19b65646857342e2af8f73d22a31df
https://doi.org/10.13182/nt99-a2947
https://doi.org/10.13182/nt99-a2947
Publikováno v:
International Journal of Radioactive Materials Transport. 9:249-255
A conservative methodology is described that would allow taking credit for burnup in the criticality safety analysis of spent nuclear fuel packages. Requirements for its implementation include isotopic and criticality validation, generation of packag
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::27b97d41e4aa5f5f68bd1ac244df7a46
https://doi.org/10.1179/rmt.1998.9.4.249
https://doi.org/10.1179/rmt.1998.9.4.249
Autor:
Robert L. Marsh, Holger Pfeifer, C. Steve Erwin, Alan E. Levin, Daniel B. Bullen, D.B. Lancaster
Publikováno v:
Nuclear Technology. 97:16-26
In this paper, uranium metal alloys were previously suggested for use in advanced pressurized water reactors; a method is proposed to select an appropriate fuel rod diameter for a uranium alloy-fueled reactor. The method attempts to isolate effects c
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::7323f5e6d8edf17030523785d4147ee6
https://doi.org/10.13182/nt92-a34622
https://doi.org/10.13182/nt92-a34622
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