Download or read book Parametric Study of Radiation Dose Rates from Rail and Truck Spent Fuel Transport Casks written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: Neutron and gamma dose rates from typical rail and truck spent fuel transport casks are reported for a variety of spent PWR fuel sources and cask conditions. The IF 300 rail cask and NLI 1/2 truck cask were selected for use as appropriate cask models. All calculations (cross section preparation, generation of spent fuel source terms, radiation transport calculations, and dose evaluation) were performed using various modules of the SCALE computational system. Conditions or parameters for which there were variations between cases include: detector distance from cask, spent fuel cooling time, the setting of fuel or neutron shielding cavities to either wet or dry, the cobalt content of assembly materials, normal fuel assemblies and consolidated cannisters, the geometry mesh interval size, and the order of the angular quadrature set. 13 refs., 6 figs., 9 tabs.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 664 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book ERDA Energy Research Abstracts written by and published by . This book was released on 1985 with total page 676 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Calculation of Radiation Dose Rates from a Spent Nuclear Fuel Shipping Cask written by and published by . This book was released on 1988 with total page 6 pages. Available in PDF, EPUB and Kindle. Book excerpt: Radiation doses from a spent nuclear fuel cask are usually from various phases of operations during handling, shipping, and storage of the casks. Assessment of such doses requires knowledge of external radiation dose rates at various locations surrounding a cask. Under current practices, dose rates from gamma photons are usually estimated by means of point- or line-source approaches incorporating the conventional buildup factors. Although such simplified approaches may at times be easy to use, their accuracy has not been verified. For example, those simplified methods have not taken into account influencing factors such as the geometry of the cask and the presence of the ground surface, and the effects of these factors on the calculated dose rates are largely unknown. Moreover, similar empirical equations for buildup factors currently do not exist for neutrons. The objective of this study is to use a more accurate approach in calculating radiation dose rates for both neutrons and gamma photons from a spent fuel cask. The calculation utilizes the more sophisticated transport method and takes into account the geometry of the cask and the presence of the ground surface. The results of a detailed study of dose rates in the near field (within 20 meters) are presented and, for easy application, the cask centerline dose rates are fitted into empirical equations at cask centerline distances up to 2000 meters from the surface of the cask.
Download or read book Energy Research Abstracts written by and published by . This book was released on 1985 with total page 1338 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Radiation Dose Rates from Consolidated Fuel in Current Generation Shipping Casks written by and published by . This book was released on 1985 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: As part of a DOE study of public risk from cask transport of consolidated and unconsolidated spent fuel cooled beyond five years, radiation dose rates from two current generation shipping casks were evaluated. The IF300 rail shipping cask (with a capacity of seven PWR assemblies) and NLI 1/2 truck shipping cask (with a capacity of one PWR assembly) were selected as appropriate cask models. A Westinghouse 17 x 17 fuel assembly with a 3.3 wt % 235U enrichment, operated at a specific power of 37.5 MW/MTU for 880 full-power days (20% downtime in history), and discharged at a burnup of 33 GWD/MTU was specified. Results for spent fuel cooling times of 5, 10, 15, and 25 years are reported here.
Download or read book Transportation Weekly Government Abstracts written by and published by . This book was released on 1986 with total page 144 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Shielding and Criticality Analyses of Phase I Reference Truck and Rail Cask Designs for Spent Nuclear Fuel written by and published by . This book was released on 1993 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This work was performed in support of the planned Phase I request for proposals (RFP) for spent nuclear fuel (SNF) transportation cask designs. The funding for this work was provided by the Office of Civilian Radioactive Waste Management (OCRWM) through its M & O contractor, TRW Environmental Safety Systems (TESS). The objective of this work was to prepare for the criticality and shielding evaluation of the Phase I cask design proposals by investigating the effect of SNF and design variables on reference cask models. Prior knowledge in this area should mitigate the analysis effort required for the bid evaluation process. The effect of SNF burnup/age characteristics on payload, the effect of initial enrichment on the radiation source and dose, and the relative effectiveness of several gamma-ray and neutron shield materials were all areas of investigation. In addition, the results of this effort provide data that can be used to assess the practicality of the RFP specifications regarding the targeted performance of the Phase I casks. Although the final RFP for the Phase I cask was never issued, this report has been issued because of its potential value in future SNF cask design efforts. Results are presented herein to determine the adequacy with respect to shielding regulations of reference designs for a truck cask containing 2 PWR or 5 BWR assemblies of standard burnup (45 GWd/MTU for PWR, 40 GWd/MTU for BWR) and 1 PWR assembly with extended burnup (55 GWd/MTU). The study also includes reference and modified rail cask designs with projected payloads of 8, 10, or 12 PWR assemblies. The burnup/age trends are analyzed in one dimension for both Pb and depleted uranium (DU) gamma-ray shields. The two-dimensional analyses concentrate on multidimensional aspects of each design and the degree to which the one-dimensional results are adequate. Both cask types are also analyzed for adequacy from a criticality safety standpoint. The results of the two-dimensional shielding analysis uphold the one-dimensional results as being an appropriate means of studying the burnup/age trends for the truck cask. These results show that the reference design for the Pb-shield truck cask is inadequate for all cases considered, while the DU-shield truck cask is capable of carrying the desired payloads. The one-dimensional shielding analysis results for the reference Pb and DU rail casks indicate substantial margins exist in the side doses for reasonable burnup/age combinations. For a Pb-cask configuration, margins exist primarily for long-cooled (15 years) fuel. For the modified Pb and DU rail casks, the 2-m dose rates offer substantial margins below the regulatory limits for all burnup values considered provided the spent fuel has cooled for e"0 years. The modified Pb and DU casks yield essentially identical results and, hence, could be considered equivalent from a shielding perspective. The criticality analyses that were performed indicate that a truck basket can be designed to provide an adequate subcritical margin for 2 PWR assemblies enriched to 5 wt %. While the 10- and 12-assembly rail cask designs are very close to the regulatory limit of 0.95 for k{sub eff}, after accounting for a 0.01 [Delta]k bias and 2 standard deviations, the limit is exceeded by about 3%. It is believed that a combination of decreased enrichments and/or increased water gaps should allow these baskets to be acceptable.
Download or read book HRIS Abstracts written by National Research Council (U.S.). Highway Research Board and published by . This book was released on 1987 with total page 614 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Geologic Repository for Disposal of Spent Nuclear Fuel and High level Radioactive Waste at Yucca Mountain written by and published by . This book was released on 1999 with total page 832 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transactions of the American Nuclear Society written by American Nuclear Society and published by . This book was released on 1989 with total page 838 pages. Available in PDF, EPUB and Kindle. Book excerpt:
Download or read book Transporting Spent Fuel written by William R. Lahs and published by . This book was released on 1987 with total page 40 pages. Available in PDF, EPUB and Kindle. Book excerpt: Shipping container response to severe highway and railway accidents conditions (See N351-399).
Download or read book Evaluation of Simplified Models for Estimating Public Dose from Spent Nuclear Fuel Shipments written by and published by . This book was released on 2015 with total page pages. Available in PDF, EPUB and Kindle. Book excerpt: This paper investigates the dose rate as a function of distance from a representative high-capacity SNF rail-type transportation cask. It uses the SCALE suite of radiation transport modeling and simulation codes to determine neutron and gamma radiation dose rates. The SCALE calculated dose rate is compared with simplified analytical methods historically used for these calculations. The SCALE dose rate calculation presented in this paper employs a very detailed transportation cask model (e.g., pin-by-pin modeling of fuel assembly) and a new hybrid computational transport method. Because it includes pin-level heterogeneity and models ample air and soil outside the cask to simulate scattering of gamma and neutron radiation, this detailed SCALE model is expected to yield more accurate results than previously used models which made more simplistic assumptions (e.g., fuel assembly treated as a point or line source, simple 1-D model of environment outside of cask). The results in this paper are preliminary and, as progress is made on developing and validating improved models, results may be subject to change as models and estimates become more refined and better information leads to more accurate assumptions.
Download or read book A Comparison of Radiation Exposures of Highway Drivers from Various Types of Radioactive Materials written by James Shuler and published by Lulu.com. This book was released on 2009-05-01 with total page 125 pages. Available in PDF, EPUB and Kindle. Book excerpt: Summaries of occupational radiation exposures to highway drivers from various types of radioactive materials. Spent fuel drivers, radiopharmaceutical drivers, low-level radioactive waste, and uranium hexafloride are examined. Domestic and foreign studies are also examined.
Download or read book Final Environmental Impact Statement for a Geologic Repository for the Disposal of Spent Nuclear Fuel and High level Radioactive Waste at Yucca Mountain Nye County Nevada Appendixes A through O written by and published by . This book was released on 2002 with total page 850 pages. Available in PDF, EPUB and Kindle. Book excerpt: The purpose of this environmental impact statement (EIS) is to provide information on potential environmental impacts that could result from a Proposed Action to construct, operate and monitor, and eventually close a geologic repository for the disposal of spent nuclear fuel and high-level radioactive waste at the Yucca Mountain site in Nye County, Nevada. The EIS also provides information on potential environmental impacts from an alternative referred to as the No-Action Alternative, under which there would be no development of a geologic repository at Yucca Mountain.
Download or read book Simple Geometry Dose Rate Benchmarks for Spent Fuel Cask Analysis written by and published by . This book was released on 1994 with total page 9 pages. Available in PDF, EPUB and Kindle. Book excerpt: Two sets of simple geometry benchmarks were analyzed using two independent Monte Carlo radiation transport codes to estimate the expected accuracies of both the spent fuel source terms and the neutron and gamma-ray transport for typical spent fuel storage/transport cask applications. The first set of dose rate measurements were performed at General Electric-Morris Operation for single, unshielded spent fuel assemblies in both dry and wet configurations. The second set of benchmark experiments carried out in Japan consisted of a series of dose rate measurements for a 252Cf neutron source and a 6°Co photon source impinging onto shields of cask material of varying thicknesses. The details of the analysis of these measurements is described herein along with comparison with experimentally obtained neutron and gamma dose rates.
Download or read book Radwaste 86 written by L. C. Ainslie and published by . This book was released on 1986 with total page 1060 pages. Available in PDF, EPUB and Kindle. Book excerpt:
