Zobrazeno 1 - 10
of 63
pro vyhledávání: '"John C. Wagner"'
Autor:
John M Scaglione, Kaushik Banerjee, Georgeta Radulescu, Justin B. Clarity, John C. Wagner, Joshua L. Peterson, Robert A Lefebvre, Kevin R Robb
Publikováno v:
Nuclear Technology. 195:124-142
We completed a novel assessment to determine the unquantified and uncredited safety margins (i.e., the difference between the licensing basis and as-loaded calculations) available in as-loaded spent nuclear fuel (SNF) casks. This assessment was perfo
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bd7aced949238945b3ac083f2fd40fb3
https://doi.org/10.13182/nt15-112
https://doi.org/10.13182/nt15-112
Autor:
Ahmad M. Ibrahim, Mohamed E. Sawan, Douglas E. Peplow, Robert E. Grove, Thomas M. Evans, Scott W. Mosher, Paul P. H. Wilson, John C. Wagner
Publikováno v:
Nuclear Science and Engineering. 181:48-59
The well-established Consistent Adjoint Driven Importance Sampling (CADIS) and the Forward Weighted Consistent Adjoint Driven Importance Sampling (FW-CADIS) hybrid Monte Carlo/deterministic techniq...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::bb58d50f49d5c486739775b832d8626c
https://doi.org/10.13182/nse14-94
https://doi.org/10.13182/nse14-94
Publikováno v:
Nuclear Technology. 188:266-279
One of the most significant remaining challenges associated with expanded implementation of burnup credit in the United States is the validation of depletion and criticality calculations used in the safety evaluation - in particular, the availability
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::906e55e18d39b44154c87b443b459248
https://doi.org/10.13182/nt13-151
https://doi.org/10.13182/nt13-151
Publikováno v:
Nuclear Technology. 188:154-171
This paper describes a depletion code validation approach for criticality safety analysis using burnup credit for actinide and fission product nuclides in spent nuclear fuel (SNF) compositions. The technical basis for determining the uncertainties in
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::41747d3f1acf242faa940d092c249b08
https://doi.org/10.13182/nt13-154
https://doi.org/10.13182/nt13-154
Autor:
John C. Wagner, William Bj J Marshall
Publikováno v:
Packaging, Transport, Storage & Security of Radioactive Material. 25:1-7
Commercial used nuclear fuel (UNF) in the USA is expected to remain in storage for periods potentially greater than 40 years. Extended storage (ES) time and irradiation to high burnup values (>45 GWd t−1) may increase the potential for fuel failure
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c04b9434c18e4749fa8ce7eb5ee7a91f
https://doi.org/10.1179/1746510914y.0000000056
https://doi.org/10.1179/1746510914y.0000000056
Publikováno v:
Nuclear Science and Engineering. 176:37-57
This paper presents a hybrid (Monte Carlo/deterministic) method for increasing the efficiency of Monte Carlo calculations of distributions, such as flux or dose rate distributions (e.g., mesh talli...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::ae85fa1ced996ef87fa8dcb18ec1176b
https://doi.org/10.13182/nse12-33
https://doi.org/10.13182/nse12-33
Publikováno v:
Nuclear Technology. 182:63-74
The potential for smuggling special nuclear material (SNM) into the United States is a major concern to homeland security, so federal agencies are investigating a variety of preventive measures, including detection and interdiction of SNM during tran
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::92984ef7c2f4abc55f8b3fd116e251d9
https://doi.org/10.13182/nt13-a15827
https://doi.org/10.13182/nt13-a15827
Publikováno v:
Nuclear Science and Engineering. 173:276-292
It is well-known that statistical estimates obtained from Monte Carlo criticality simulations can be adversely affected by cycle-to-cycle correlations in the fission source, which can lead to estim...
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::c736724a84abbb0e1b06a834e1bafb54
https://doi.org/10.13182/nse11-104
https://doi.org/10.13182/nse11-104
Autor:
George F. Flanagan, Emilian L. Popov, Jess C. Gehin, Ian C Gauld, Dean Wang, Graydon L. Yoder, John C. Wagner, Prashant K. Jain, Larry J. Ott, Juan J. Carbajo, Matthew W. Francis
Publikováno v:
Nuclear Technology. 180:205-215
A study on the Fukushima Daiichi nuclear power station spent-fuel pool (SFP) at Unit 4 (SFP4) is presented in this paper. We discuss the design characteristics of SFP4 and its decay heat load in detail and provide a model that we developed to estimat
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::09e271ae103737b01d34afad4478e2ab
https://doi.org/10.13182/nt12-a14634
https://doi.org/10.13182/nt12-a14634
Publikováno v:
Progress in Nuclear Science and Technology. 2:808-814
** This paper provides a review of the hybrid (Monte Carlo/deterministic) radiation transport methods and codes used at the Oak Ridge National Laboratory and examples of their application for increasing the efficiency of real-world, fixed-source Mont
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=doi_________::8416d645b2eb63f4fb8542c0351f4062
https://doi.org/10.15669/pnst.2.808
https://doi.org/10.15669/pnst.2.808