DESIGN REPORT FOR NMSR PRESSURIZED WATER LOOP AT ORR
A pressurized water loop constructed in the Oak Ridge Research Reactor for use in the Maritime Reactor Program is described. Irradiation testing of pressure vessel material specimens and several sets of fuel pins for the NS "Savannah" Nuclear Merchant Ship Reactor (NMSR) was completed. Operating conditions for the fuel tests nominally were 500 deg F and 1750 psig. The loop has capability for operation at 650 deg F, 2500 psig, with a maximum water flow rate of 80 gpm, and heat removal in excess of 150 kw. Design features include convenient access for insertion and removal of test specimens, efficient use of equipment cubicle space, and reliable operation. The loop is entirely constructed of 300-series stainless steel. A bypass purification and sampling system affords continuous water-chemistry control, and provision was made for attachment of special equipment for chemistry studies. Fuel and material test specimens are irradiated in the space provided by two tubes, 1.5 in. ID by 24 in. long, in positions A-1 and A-2 of the ORR core. The maximum unperturbed thermal-neutron flux is approximately 7.5 x 10 to the 13th power neutrons/cm squared sec and the peak gamma heat about 5 w/g with the ORR operating at 30 Mw. (Author)
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Corporate Authors:
Oak Ridge National Laboratory
Department of Energy
Oak Ridge, TN United States 37831 -
Authors:
- Dudley, I T
- Tidwell, D E
- TRAUGER, D B
- Publication Date: 1962-1-5
Media Info
- Pagination: 66 p.
Subject/Index Terms
- TRT Terms: Design; Equipment tests; Nuclear powered ships; Nuclear reactors; Operations
- Old TRIS Terms: Nuclear reactor design; Nuclear reactor operation; Nuclear reactor testing
- Subject Areas: Administration and Management; Design; Marine Transportation; Vehicles and Equipment;
Filing Info
- Accession Number: 00026598
- Record Type: Publication
- Source Agency: National Technical Information Service
- Contract Numbers: W-7405-eng-26
- Files: TRIS
- Created Date: May 4 1973 12:00AM