Zobrazeno 1 - 10
of 21
pro vyhledávání: '"G.E. Bosler"'
Publikováno v:
Conference Record of the 1991 IEEE Nuclear Science Symposium and Medical Imaging Conference.
Instruments developed for safeguards in the domestic nuclear industry to nondestructively assay nuclear materials are being used in unattended and remote monitoring applications. In large facilities, such instruments can be combined with more classic
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https://explore.openaire.eu/search/publication?articleId=doi_dedup___::9913b7f093319e10f4f38fe50547b957
https://doi.org/10.1109/nssmic.1991.259124
https://doi.org/10.1109/nssmic.1991.259124
This manual describes the design features and operating characteristics of the research reactor fork. The system includes an ion chamber for gross gamma-ray counting, fission chambers for neutron counting, and a collimated high-resolution spectroscop
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https://explore.openaire.eu/search/publication?articleId=doi_________::795c6b27c3398d07a77ea0402f4e5720
https://doi.org/10.2172/10107365
https://doi.org/10.2172/10107365
This is an interim report of a study concerning the potential application of nondestructive measurements on irradiated light-water-reactor (LWR) fuels at spent-fuel storage facilities. It describes nondestructive measurement techniques and instrument
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https://explore.openaire.eu/search/publication?articleId=doi_________::db43a7d7d7eb6e91ea368ba9aed21d82
https://doi.org/10.2172/5253974
https://doi.org/10.2172/5253974
Autor:
G.E. Bosler
A technique for performing calculationally assisted evaluations of shift-register coincidence counter data is discussed. An example of a typical application for some high mass PuO/sub 2/ samples is presented. Methods for applying the technique to gen
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https://doi.org/10.2172/6353680
https://doi.org/10.2172/6353680
This report describes calculations that examine the sensitivity of actinide isotopes to various reactor parameters. The impact of actinide isotope build-up, depletion, and decay on the neutron source rate in a spent-fuel assembly is determined, and c
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https://doi.org/10.2172/5113091
https://doi.org/10.2172/5113091
Nondestructive measurement of the passive neutron signatures of irradiated light-water reactor fuel assemblies is a rapid and simple technique for verifying operator-declared exposure values. Fuel assemblies from four different reactor facilities hav
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https://explore.openaire.eu/search/publication?articleId=doi_________::ba6be153513da8784b46a2afe7d65187
https://doi.org/10.2172/5490746
https://doi.org/10.2172/5490746
The LASIP-III code was developed for processing Version III standard interface data files which have been specified by the Committee on Computer Code Coordination. This processor performs two distinct tasks, namely, transforming free-field format, BC
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https://explore.openaire.eu/search/publication?articleId=doi_________::732ed1321c74b210e27f98fe5e06a1ab
https://doi.org/10.2172/7189584
https://doi.org/10.2172/7189584
Results of S/sub N/ and Monte Carlo one-dimensional neutron/gamma-ray transport calculations for conceptual designs of the INESCO RIGGATRON, a Tokamak device using ohmic heating to induce fusion, are detailed. Using various plasma, coil, and blanket
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https://doi.org/10.2172/5078152
https://doi.org/10.2172/5078152