Naval Reactors History Database (nrhdb)
Favorites (0)
Search:
'S2G' in subject
rss icon RSS | Modify Search | New Search | nrhdb Home
Results:  4 itemsBrowse by Facet | Title
Sorted by:  
Page: 1
Subject
Naval Reactors (4)
S2G (4)
USS Seawolf (SSN-575) (3)
Nuclear engineering (1)
S1G (1)
Date
expand2012 (1)
1959 (1)
expand1957 (1)
expand1955 (1)
Type
Image (2)
Text (2)
1Title:  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
2Title:  The USS Seawolf underway Add
 Summary:  The USS Seawolf underway in 1977. During her early years of operations in the late 1950s, the Seawolf was powered by an S2G (sodium-cooled, intermediate range) reactor plant designed by General Electric. Because of difficulties in operating this plant and the demonstrated superiority of the pressurized water reactor (PWR) design, the Seawolf's sodium-cooled plant was removed and replaced with an S2W PWR plant at Electric Boat in 1958-60. 
 Source:  http://en.wikipedia.org/wiki/File:USS_Seawolf_%28SSN-575%29.jpg 
 Reference:  Polmar, Norman. Atomic Submarines. London: Van Nostrand, 1963, pages 106-109. 
 Date:  18 October 1957 
 Subject(s):  S2G | USS Seawolf (SSN-575) | Naval Reactors 
 Type:  Image 
 Format:  JPEG 
 Similar items:  Find
3Title:  USS Seawolf at launching - Submarine Intermediate Range (SIR) reactor Add
 Summary:  The second commissioned nuclear-powered submarine was the USS Seawolf. At the time of her commissioning in March 1957, the Seawolf was powered by an S2G reactor plant, which followed the design and construction of the S1G land-based prototype plant. The plant used sodium as the coolant and beryllium as a moderator and reflector. One important advantage of using sodium as the coolant and heat transfer medium is that higher coolant and secondary steam temperatures are possible, which results in higher thermal efficiency. Additionally, the primary system can be maintained at a reliatively low pressure. Both of these factors enabled primary and secondary components to be lighter (compared with those installed in a pressurized water reactor plant). However, operation of the S1G and S2G plants revealed severe design problems, including primary-to-secondary leakage (and the potential of sodium reacting with water in the secondary system). In 1959, the Seawolf's S2G plant was removed and replaced with an S2Wa pressurized water reactor plant. 
 Source:  http://www.navsource.org/archives/08/08575a.htm 
 Reference:  Ragheb, Madgi. Nuclear Marine Propulsion. 20 July 2011 [http://tinyurl.com/3fm3azu]. 
 Date:  21 July 1955 
 Subject(s):  S2G | USS Seawolf (SSN-575) | Naval Reactors 
 Type:  Image 
 Format:  JPEG 
 Similar items:  Find
4Title:  The USS Seawolf sodium-cooled reactor Add
 Summary:  The text of a May 2012 speech by Eric Loewen of the American Nuclear Society, which focused on the sodium cooled intermediate range reactors designed and developed by General Electric for naval propulsion. While there are some errors in the text, Loewen describes sodium cooled reactor technology and components such as electromagnetic pumps. He provides some unique insights into the construction of the S1G and S2G naval plants. Similar to the Manhattan Engineer District project, the development of naval nuclear propulsion followed a parallel path with the Pressurized Water Reactor (PWR), developed by Westinghouse and the sodium cooled, Submarine Intermediate Rector (SIR), developed by General Electric. Loewen notes that the SIR offered two important advantages: "the sodium cooled knowledge base was further advanced than the PWR, and the sodium cooled reactor did have higher steam cycle efficiency" (3). He also describes some of the weaknesses of the SIR reactor, including the use of 347 stainless steel (347SS) in the superheaters and the "adverse affects of sodium" upon 347SS. Bypassing the superheaters led to higher-than-expected uranium depletion as the plant operated with lower steam temperatures and pressures (5). In reviewing the Soviet navy's use of liquid metal cooled plants, Loewen notes another weakness of the SIR: external heaters must keep the primary loop warm during reactor shutdown periods in order to keep the coolant from solidifying. Errors include the power rating of the Shippingport civilian power plant (initial rating, 60 MW) and the moderator for the S1G and S2G plants (which were beryllium, not carbon). 
 Source:  http://www.new.ans.org/about/officers/docs/seawolf_sfr_sea_story_051712.pdf 
 Date:  17 May 2012 
 Subject(s):  S1G | S2G | USS Seawolf (SSN-575) | Naval Reactors 
 Type:  Text 
 Format:  PDF 
 Similar items:  Find

nrhdb Home