Author: J. C. RymanPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 148
Book Description
Fuel Inventory and Afterheat Power Studies of Uranium-fueled Pressurized Water Reactor Fuel Assemblies Using the SAS2 and ORIGEN-S Modules of Scale with an ENDF/B-V Updated Cross Section Library
Author: J. C. RymanPublisher:
ISBN:
Category : Nuclear fuels
Languages : en
Pages : 148
Book Description
Energy Research Abstracts
Author: Fuel inventory and afterheat power studies of uranium-fueled pressurized water reactor ... section library
Author: The Scale Analysis Sequence for LWR Fuel Depletion
Author: Publisher:
ISBN:
Category :
Languages : en
Pages : 23
Book Description
The SCALE (Standardized Computer Analyses for Licensing Evaluation) code system is used extensively to perform away-from-reactor safety analysis (particularly criticality safety, shielding, heat transfer analyses) for spent light water reactor (LWR) fuel. Spent fuel characteristics such as radiation sources, heat generation sources, and isotopic concentrations can be computed within SCALE using the SAS2 control module. A significantly enhanced version of the SAS2 control module, which is denoted as SAS2H, has been made available with the release of SCALE-4. For each time-dependent fuel composition, SAS2H performs one-dimensional (1-D) neutron transport analyses (via XSDRNPM-S) of the reactor fuel assembly using a two-part procedure with two separate unit-cell-lattice models. The cross sections derived from a transport analysis at each time step are used in a point-depletion computation (via ORIGEN-S) that produces the burnup-dependent fuel composition to be used in the next spectral calculation. A final ORIGEN-S case is used to perform the complete depletion/decay analysis using the burnup-dependent cross sections. The techniques used by SAS2H and two recent applications of the code are reviewed in this paper. 17 refs., 5 figs., 5 tabs.
Calculation of Fuel Loss from Vented Nuclear Fuel Elements for Space Power Reactors
Author: Richard E. GluyasPublisher:
ISBN:
Category : Depleted uranium
Languages : en
Pages : 42
Book Description
Spent Fuel Storage Facts Booklet
Author: United States. Department of EnergyPublisher:
ISBN:
Category : Spent reactor fuels
Languages : en
Pages : 68
Book Description
Spent fuel storage requirements
Author: United States. Department of Energy. Division of Spent Fuel Storage and TransferPublisher:
ISBN:
Category :
Languages : en
Pages : 20
Book Description
SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary
Author: LWR spent fuel disposition capabilities
Author: United States. Energy Research and Development Administration. Division of Nuclear Fuel Cycle and ProductionPublisher:
ISBN:
Category :
Languages : en
Pages : 36
Book Description
Use of the SRE Fuel in an Exponential Experiment
Author: R. A. LaubensteinPublisher:
ISBN:
Category : Nuclear fuel elements
Languages : en
Pages : 14
Book Description