Naval Reactors History Database (nrhdb)
Favorites (0)
Search:
Nuclear engineering in subject [X]
rss icon RSS | Modify Search | New Search | nrhdb Home
Results:  36 itemsBrowse by Facet | Title
Sorted by:  
Page: Prev  1 2 3 4  Next
Date
unknown (6)
expand2006 (3)
expand2005 (1)
2002 (1)
1993 (1)
1986 (1)
1979 (1)
1975 (1)
expand1964 (5)
1961 (1)
expand1960 (1)
1959 (1)
expand1958 (1)
1957 (3)
1956? (1)
expand1956 (4)
1955? (2)
1955 (1)
1954? (1)
Type
Text (20)
Image (16)
21Title:  Naval Reactors Prime Contractor Team (NRPCT) Experiences and considerations with irradiation test performance in an international environment Add
 Summary:  This document describes the NRPCT's efforts to identify reactors worldwide for irradiation testing of materials expected to be included in a Prometheus reactor. The Experimental Fast Reactor JOYO in O-arai, Japan was identified as the best facility to support irradiation testing for the project (which was created to support space reactor development for solar exploration; the project ended in 2005). JOYO is a sodium-cooled Liquid Metal Reactor (LMR). Detailed planning information for reactor materials irradiation testing is included in the report. 
 Source:  http://www.osti.gov/bridge/purl.cover.jsp?purl=/883694-B0koQW/ 
 Date:  15 February 2006 
 Subject(s):  Project Prometheus | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
22Title:  Naval reactors physics handbook. Volume 1, Selected basic techniques Add
 Chapter title:  "Reactor physics and its application to nuclear power reactors" 
 Summary:  This chapter, written by physicist Alvin Radkowsky, summarizes the design challenges of submarine reactors in comparison with the natural uranium graphite reactors that had been designed and built during World War II. For example, Radkowsky describes the novelty ("close spacing") and design complexity of the control rod arrangement in PWRs (4). He also describes the parallel track of reactor development overseen by NR, with the intermediate range research supporting the S1G and S2G reactors performed by the Knolls Atomic Power Laboratory; and, research supporting the Submarine Thermal Reactor (STR, or the S1W and S2W reactors) led by the Bettis Atomic Power Laboratory. He notes that while the intermediate range reactor approach had, by 1964, been abandoned in favor of the pressurized water reactor (PWR) design, that "fuel loading densities are often sufficiently high [so] that a substantial fraction of the fissions occurs above thermal neutron energies" (2). As a result, some research relating to the intermediate range reactor could be applied to the design of PWRs. Radkowsky also summarizes some design contrasts between submarine reactors and the reactors for the Shippingport Atomic Power Station, with the latter relying on fuels with high U-238 composition. 
 Source:  http://www.osti.gov/bridge 
 Date:   1964 
 Subject(s):  Reactor physics | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
23Title:  Reactor shielding design manual Add
 Chapter title:  "Introduction and outline of basic shielding theory" 
 Summary:  This manual, edited by Theodore Rockwell of the early Naval Reactors group, is designed to provide an engineering overview of shielding design issues. The introductory chapter provides a pathfinder for the manual as a whole. Rockwell defines "shield engineering" as "the art of [lowering radiation levels] within specified limits of weight, volume, or cost" (4). He notes that neutron and gamma radiation are the primary focus of shield design and describes methods (such as the use of specific materials and shield compositions) used to achieve neutron and gamma-ray attenuation. 
 Source:  http://www.osti.gov/bridge 
 Date:   1956 
 Subject(s):  Reactor shielding | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
24Title:  Documentation of Naval Reactors papers and presentations for the Space Technology and Applications International Forum (STAIF) 2006 Add
 Summary:  This document contains information on the presentations and papers (24 in all) prepared by the Knolls and Bettis Atomic Power laboratories for the Space Technology and Applications International Forum (STAIF) 2006 conference. These presentations describe the work of Naval Reactors and its contractor laboratories, Bettis and Knolls, for NASA's Project Prometheus, which was created to investigate the possible use of nuclear-powered systems for long duration space missions. At the time of the project, Naval Reactors was designated by the Department of Energy as the lead agency for the development of civilian space reactor systems. NR engaged the two contractor laboratories to investigate issues related to deep space reactors. The presentations cover topics such as reactor design, reactor instrumentation, and plant materials. 
 Source:  http://www.osti.gov/bridge 
 Date:   2006 
 Subject(s):  Project Prometheus | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
25Title:  Defueling the S2G reactor Add
 Summary:  This report describes the defueling of Seawolf's S2G reactor plant at Electric Boat in January 1959. This defueling was accomplished as part of the Seawolf's conversion from the sodium-cooled, intermediate range S2G reactor to a pressurized water reactor (PWR), owing to problems with the sodium-cooled design. These serious problems, which plagued the S1G (or Mark A) prototype and S2G shipboard plants, demonstrated the clear superiority of the PWR design in submarine propulsion. The report describes the importance of training (for Knolls Atomic Power Laboratory, Electric Boat, and Navy personnel who worked on the defueling) consisting of lectures and dry-runs that took place in the fall of 1958. The dry-runs enabled workers to check the condition of refueling equipment and time estimates for the completion of maintenance steps. (The summary on page 18 describes the importance of dry-runs and recommends some best practices for accomplishing them.) The dry-runs also contributed to the success in minimizing radiation exposure when the refueling was performed: "No individuals were exposed to more than the maximum permissible daily dose, 50 [millirem]" (3). The report provides an overview of the steps performed in defueling the sodium-cooled reactor. It also provides a summary of lessons learned, including: failure of a brazed joint in a cup designed to catch sodium drippage from fuel elements, which was identified during the dry run operation and fixed by using cups with welded joints; and, gas leakage from a transfer cask. Also, there was a report of difficulty in grappling an S2G fuel rod that was being removed, due to wear in the grappling equipment. After completion of the refueling, the S2G's fuel rods were shipped via train to the Idaho National Laboratory's Expended Core Facility. 
 Source:  http://www.osti.gov/bridge 
 Date:   1959 
 Subject(s):  S2G | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
26Title:  TMI-2 Lessons Learned Task Force: Status report and short-term recommendations Add
 Summary:  This document, known as NUREG-0578, was created by the Lessons Learned Task Force, an interdisciplinary group formed by the Nuclear Regulatory Commission in the aftermath of the Three Mile Island (TMI-2) accident, which occurred on 28 March 1979. Of particular interest is the section on short-term recommendations, in which the task force proposes changes to operating procedures given the circumstances of the TMI-2 accident (a loss of feed in the secondary system, followed by a loss of coolant accident [LOCA] in the primary system of the pressurized water reactor, with resulting core damage). Several recommendations stand out. First, providing emergency power for critical services, such as pressurizer level indicator, pressurizer heaters, and power-operated control values. Second, performing periodic checking of primary system safety and relief valves. Third, and critically, ensuring that operators are trained to better diagnose "low reactor coolant level and inadequate core cooling using existing reactor instrumentation (flow, temperature, power, etc.)" (8). While the recommendations as a whole are focused on commercial power reactor plants, many of these operational recommendations are applicable to the pressurized water reactors operated in the Navy's submarine and surface force. 
 Source:  http://www.osti.gov/bridge 
 Date:   1979 
 Subject(s):  Reactor safety | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
27Title:  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 
 Similar items:  Find
28Title:  An evaluation of data on zirconium-uranium alloys Add
 Summary:  This document, compiled by Frank Rough of the Battelle Memorial Institute, contains a review of information on zirconium-uranium alloys. As noted in the introduction, "because of the similar properties and fabricational characteristics of these materials, the cladding of zirconium-uranium alloys with Zircaloy has proven to be very successful, with good metallurgical bonds being obtained" (7). This review addresses issues such as the corrosion of zirconium-uranium alloys in high temperature/high pressure systems and the impact of neutron irradiation upon these alloys. These and other issues are addressed and mapped to an extensive bibliography. As described by historians Thomas Hewlett and Francis Duncan in their book Nuclear Navy, Naval Reactors was deeply involved in the development of zirconium production in the United States, with the need to produce tonnage lots of zirconium to support early prototype and submarine reactor core construction. Beyond this, improvements in the technology were needed, such as the development of Zircaloy-2, a material superior to the zirconium-uranium alloy used in the first Mark I/S1W core. 
 Source:  http://www.osti.gov/bridge 
 Date:   1955 
 Subject(s):  Zirconium/Zircaloy | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
29Title:  Mechanical properties of Zircaloy-2 Add
 Summary:  To summarize: "Zircaloy-2 is a zirconium-tin alloy developed for use in water cooled nuclear reactors. It possesses good corrosion resistance to high-temperature water, excellent nuclear characteristics, and sufficiently good mechanical properties for use as a structural material in reactor cores and as a fuel element material" (1). The report analyzes changes in Zircaloy-2 properties caused by changes in operating conditions, including temperature, hydrogen concentration, and the presence of small notches in the material. As noted in the Hewlett/Duncan book, Nuclear Navy, "the study of zirconium alloys [in the first half of the 1950s] resulted in the development of a new material called Zircaloy-2, which was far superior to the material used in the [Mark I/S1W] core." 
 Source:  http://www.osti.gov/bridge 
 Date:   1961 
 Subject(s):  Zirconium/Zircaloy | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
30Title:  Technical progress report: Pressurized water reactor program (September 9 to October 20, 1955) Add
 Summary:  This 1955 report provides a technical update on Westinghouse's work with pressurized water reactor development in the context of the Shippingport Atomic Power Station project. At this time, Westinghouse was the leading designer and builder of naval nuclear propulsion plants, having constructed the Mark I (S1W prototype) and Mark II (Nautilus shipboard) reactors, and designed the S5W submarine fleet reactor. Additionally, Westinghouse was working under the direction of the Naval Reactors organization on the design and construction of the Shippingport Atomic Power Station plant, the first large-scale nuclear power plant that provided power for civilian use. The report describes Westinghouse.s progress (and work with other vendors) in the design and fabrication of reactor core and primary and secondary system components for the Shippingport plant. 
 Source:  http://www.osti.gov/bridge 
 Date:  circa 1955 
 Subject(s):  Shippingport Atomic Power Station | Nuclear engineering | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find
Page: Prev  1 2 3 4  Next

nrhdb Home