Naval Reactors History Database (nrhdb)
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 Title:  Packaged, defueled submarine reactor compartments at the Hanford Site Add
 Summary:  The defueled and packaged reactor compartments removed from decommissioned submarines are stored in trench 94 at the Department of Energy's Hanford Site. The compartments are currently stored in open dry storage and will eventually be buried in the trench. This storage is the final step in the Ship-Submarine Recycling Program (SRP), which handles the disposal of decommissioned nuclear vessels. 
 Source:  http://www.navsource.org/archives/08/08637.htm 
 Date:   2003 
 Subject(s):  Hanford Site | Ship-Submarine Recycling Program (SRP) | Naval Reactors 
 Type:  Image 
 Format:  JPEG 
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 Title:  Photographs: Written historical and descriptive data Add
 Summary:  This document provides a historical overview of the Shippingport Atomic Power Station, which achieved criticality on December 2, 1957. It describes Admiral Hyman Rickover's role in the plant's design and development. In approaching plant design, the report notes Rickover's "conservative design philosophy" and emphasis on reactor safety (7). The station's first reactor design was a pressurized water reactor (PWR), with Rickover, his Naval Reactors organization, and Westinghouse drawing upon the lessons in the design and development of the S1W (Nautilus prototype) plant, also a PWR. The basics of the PWR's seed-blanket core design are described in the document, as well as innovative aspects of the Shippingport plant that were widely adopted in the commercial nuclear power industry, including the use of "reactor containment, a structure which housed in a series of large, interconnected, vapor-tight vessels all parts of the plant containing the reactor and primary system" (3). Also, "the choice of uranium dioxide and zircaloy tubing was crucial in the history of civilian power reactors. The materials proved so successful that they were widely adopted in the civilian power industry" (10). The document also describes the Light Water Breeder Reactor (LWBR) core that was first used in operation in 1977: "Shippingport began operating on a thorium-uranium 233 core to demonstrate the feasibility of breeding in a water-cooled reactor; that is, producing more reactor fuel than was consumed" (3). The document concludes with a bibliographic essay that provides information on the Shippingport plant, including its construction, operation, and decommissioning. 
 Source:  http://lcweb2.loc.gov/pnp/habshaer/pa/pa1600/pa1658/data/pa1658data.pdf 
 Date:   unknown  
 Subject(s):  Light Water Breeder Reactor (LWBR) | Shippingport Atomic Power Station | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  Pressure vessel and piping codes applicable to the PWR reactor plant Add
 Summary:  This document provides information on standards compliance for the pressurized water reactor (PWR) installed in the Shippingport Atomic Power Station at the time of publication. The ASME standard, Boiler and Pressure Vessel Code, sections I and VIII, are referenced in the compliance summary, which maps code compliance to specific areas and components of the reactor plant. 
 Source:  http://www.osti.gov/bridge 
 Date:   1957 
 Subject(s):  Shippingport Atomic Power Station | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  Pressurized-water naval nuclear propulsion system Add
 Summary:  A simplified view of the major primary and secondary components in a naval nuclear propulsion plant. The fuel elements, containing Uranium-235 pellets, are enclosed in the reactor vessel. Pressurized water is used to moderate neutrons in the reactor core and serves as the heat transfer medium. Heated water moves to the steam generator, where the heat transfer takes place between the primary and secondary loops. The main coolant pump then returns the relatively cool water to the reactor core. The pressurizer enables primary loop pressure control through heaters (to increase pressure) and spray (to reduce pressure). The steam produced in the steam generator is used to drive turbines for propulsion and electrical power. 
 Source:  http://www.fas.org/man/dod-101/sys/ship/eng/reactor.html 
 Reference:  Hewlett, Richard G., and Francis Duncan. Nuclear Navy, 1946-1962. Chicago: University of Chicago Press, 1974, pages 131-135. 
 Date:   unknown  
 Subject(s):  Nuclear engineering | Naval Reactors 
 Type:  Image 
 Format:  JPEG 
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 Title:  Project Prometheus final report Add
 Summary:  This report describes Project Prometheus, the goal of which was "to develop a Deep Space Vehicle (DSV) for outer solar system robotic exploration missions that would combine a safe, reliable, Space Nuclear Reactor with electric propulsion." Naval Reactors was designated by the Department of Energy as the lead agency for the development of civilian space reactor systems and served as a NASA partner in this project. Project Prometheus was cancelled in 2005. 
 Source:  http://hdl.handle.net/2014/38185 
 Date:   2005 
 Subject(s):  Project Prometheus | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  Project Prometheus Reactor Module final report Add
 Summary:  This report describes the work of the Naval Reactors program's contractor laboratories - the Knolls Atomic Power Laboratory and the Bettis Atomic Power Laboratory - in NASA's Project Prometheus. Naval Reactors worked as NASA's partner in the design of a civilian space reactor for a 15-20 year mission. The first identified mission was the Jupiter Icy Moons Orbiter (JIMO). Five reactor designs were evaluated by Naval Reactors, with the direct gas Brayton plant deemed the most promising design. NR investigated a number of issues, including plant design, instrumentation and control, and core and plant materials. In performing this research, Naval Reactors determined that the existing state of reactor technology did not support the creation of a plant that would enable mission goals to be met. The Prometheus project was ended in 2005. 
 Source:  http://www.osti.gov/bridge/purl.cover.jsp?purl=/884680-LsvaFN/ 
 Date:   2006 
 Subject(s):  Project Prometheus | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  The proposed Fissile Material Cutoff Treaty (FMCT) and its potential impact on U.S. Navy nuclear propulsion programs Add
 Summary:  This Naval Postgraduate School thesis, written by Marion Burgess, Jr., examines the possible impact of the Fissile Material Cut-off Treaty (FMCT) upon the Navy's nuclear propulsion program. Burgess notes that the United States' naval nuclear reactors use enriched uranium, material that falls under the limits defined in FMCT. For a host of reasons, including verification impracticalities, the author asserts that "the United States government should not, and probably will not, endorse an FMCT that would affect the production of fissile materials for naval nuclear propulsion" (56). 
 Source:  http://www.worldcat.org/title/proposed-fissile-material-cutoff-treaty-fmct-and-its-potential-impact-on-us-navy-nuclear-propulsion-programs/oclc/610056176 
 Date:   2010 
 Subject(s):  Highly enriched uranium (HEU) | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  Propulsion systems for Navy ships and submarines Add
 Summary:  This letter includes a July 2006 General Accounting Office review of naval propulsion systems. It includes details on some of the technical advances in nuclear propulsion, including "eliminat[ing] the need for refueling newer submarines, such as the Virginia class submarines" and significantly-reduced operator manpower requirements (2). It also describes technical advances in conventional propulsion systems. The letter summarizes the findings and limitations of the "quick look" report created by Naval Reactors in 2005, which attempted to fix the "fiscal break-even point" for the application of nuclear propulsion (2). Appended to the letter are some PowerPoint slides from a March 2005 GAO briefing to members of Congress on naval propulsion systems. 
 Source:  http://www.fdsys.gov/ 
 Date:  06 July 2006 
 Subject(s):  Naval Reactors 
 Type:  Text 
 Format:  PDF 
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 Title:  Public scoping meeting: Environmental Impact Statement for the recapitalization of infrastructure supporting naval spent nuclear fuel handling and examination at the Idaho National Laboratory Add
 Summary:  An informational brochure that describes the Spent Fuel Handling Recapitalization Project at the Expended Core Facility. It provides an overview of ECF's operations and the importance of spent fuel processing activities to the Naval Reactors program. 
 Source:  http://www.ecfrecapitalization.us/ 
 Date:   2010 
 Subject(s):  Expended Core Facility | Naval Reactors 
 Type:  Text 
 Format:  PDF 
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