BWR/4 and BWR/5 Fuel Design PDF Download
Are you looking for read ebook online? Search for your book and save it on your Kindle device, PC, phones or tablets. Download BWR/4 and BWR/5 Fuel Design PDF full book. Access full book title BWR/4 and BWR/5 Fuel Design by R. J. Grossenacher. Download full books in PDF and EPUB format.
Author: R. J. Grossenacher
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: R. J. Grossenacher
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages :
Get Book Here
Book Description
Author: National Research Council
Publisher: National Academies Press
ISBN: 0309096472
Category : Political Science
Languages : en
Pages : 126
Get Book Here
Book Description
In response to a request from Congress, the Nuclear Regulatory Commission and the Department of Homeland Security sponsored a National Academies study to assess the safety and security risks of spent nuclear fuel stored in cooling pools and dry casks at commercial nuclear power plants. The information provided in this book examines the risks of terrorist attacks using these materials for a radiological dispersal device. Safety and Security of Commercial Spent Nuclear Fuel is an unclassified public summary of a more detailed classified book. The book finds that successful terrorist attacks on spent fuel pools, though difficult, are possible. A propagating fire in a pool could release large amounts of radioactive material, but rearranging spent fuel in the pool during storage and providing emergency water spray systems would reduce the likelihood of a propagating fire even under severe damage conditions. The book suggests that additional studies are needed to better understand these risks. Although dry casks have advantages over cooling pools, pools are necessary at all operating nuclear power plants to store at least the recently discharged fuel. The book explains it would be difficult for terrorists to steal enough spent fuel to construct a significant radiological dispersal device.
Author: International Atomic Energy Agency
Publisher:
ISBN: 9789201067036
Category : Nuclear power plants
Languages : en
Pages : 76
Get Book Here
Book Description
This is the twenty-fourth edition of Reference Data Series No. 2, which presents the most recent reactor data available to the IAEA. It contains summarized information as of the end of 2003 on: (1) power reactors operating or under construction, and shut down; and (2) performance data on reactors operating in the IAEA Member States, as reported to the IAEA. The information is collected by the Agency through designated national correspondents in the Member States. The replies are used to maintain the IAEA's Power Reactor Information System (PRIS).
Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 13
Get Book Here
Book Description
The PATHS (PARCS Advanced Thermal Hydraulic Solver) code was developed at the University of Michigan in support of U.S. Nuclear Regulatory Commission research to solve the steady-state, two-phase, thermal-hydraulic equations for a boiling water reactor (BWR) and to provide thermal-hydraulic feedback for BWR depletion calculations with the neutronics code PARCS (Purdue Advanced Reactor Core Simulator). The simplified solution methodology, including a three-equation drift flux formulation and an optimized iteration scheme, yields very fast run times in comparison to conventional thermal-hydraulic systems codes used in the industry, while still retaining sufficient accuracy for applications such as BWR depletion calculations. Lastly, the capability to model advanced BWR fuel designs with part-length fuel rods and heterogeneous axial channel flow geometry has been implemented in PATHS, and the code has been validated against previously benchmarked advanced core simulators as well as BWR plant and experimental data. We describe the modifications to the codes and the results of the validation in this paper.
Author: R. H. S. Winterton
Publisher: Elsevier
ISBN: 1483145247
Category : Technology & Engineering
Languages : en
Pages : 206
Get Book Here
Book Description
Thermal Design of Nuclear Reactors
Author: United Engineers & Constructors, inc
Publisher:
ISBN:
Category : Boiling water reactors
Languages : en
Pages : 218
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Radioactive waste disposal in the ground
Languages : en
Pages : 308
Get Book Here
Book Description
Author:
Publisher:
ISBN:
Category : Nuclear energy
Languages : en
Pages : 1174
Get Book Here
Book Description
Author: United States. Energy Research and Development Administration
Publisher:
ISBN:
Category : Medicine
Languages : en
Pages : 906
Get Book Here
Book Description
Author: Tyler Shawn Ellis
Publisher:
ISBN:
Category :
Languages : en
Pages : 183
Get Book Here
Book Description
Sobering electricity supply and demand projections, coupled with the current volatility of energy prices, have underscored the seriousness of the challenges which lay ahead for the utility industry. This research addresses the impending global need for electricity through the development of advanced annular fuel designs with both internal and external cooling which can achieve higher power densities and hence, higher electricity output from the same basic reactor vessel and containment. Therefore the objectives of this project are to determine the optimal geometrical design parameters of an annular fuel assembly for both PWRs and BWRs for the purpose of achieving maximum power density. It is theorized that utility companies can utilize this design through either retrofitting of their existing reactor facilities or incorporation of the fuel design into new plant concepts. For the case of annular fuel for PWRs, a high performance uranium nitride fuel assembly concept capable of achieving a 50% higher power density was successfully developed. It is shown that a 5% enriched UN annular-fuel assembly can operate at 150% power density for about 50 effective-full-power-days more than that of the nominal 17xl7 solid-fuel-pin assembly operating at 100% power density. Furthermore, neutronic simulation times of this assembly was reduced from approximately 2 days per simulation for a Monte Carlo based analysis to approximately 2 minutes for a deterministic based simulation via the development of an appropriate correction factor for the CASMO-4 neutron transport code. It was shown that a 25% increase in U238 number density for the un-poisoned pins and a 35% increase for the 10 weight percent gadolinium nitride poisoned pins produced the optimal plutonium tracking and infinite multiplication factor simulation.
