DESIGN REPORT FOR NMSR PRESSURIZED WATER LOOP AT ORR

Technical Report · Mon Jan 01 04:00:00 EST 1962

DOI:https://doi.org/10.2172/4725705· OSTI ID:4725705

Dudley, I. T.; Tidwell, D. E.; Trauger, D. B.

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 materinl 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 equipmert cubicle space, and reliable operation. The loop is entirely constructed of 300-series stainless steel. A bypass purification and sampling system affords continuous waterchemistry 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 thermalneutron flux is approximately 7.5 x 10/sup 13 neutrons/cm/sup 2/. sec and the peak gamma heat about 5 w/g with the ORR operating at 30 Mw. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• DOE Contract Number: W-7405-ENG-26
• NSA Number: NSA-17-009852
• OSTI ID: 4725705
• Report Number(s): ORNL-3188
• Country of Publication: United States
• Language: English

Related Subjects

BYPASS
CLEANING
CONTROL
FUELS
GAMMA RADIATION
HEATING
IN PILE LOOPS
IRRADIATION
LABORATORY EQUIPMENT
LIQUID FLOW
MATERIALS TESTING
MONITORING
NEUTRON FLUX
ORR
PLANNING
POWER
PRESSURE
PRESSURE VESSELS
PROPULSION
QUALITATIVE ANALYSIS
REACTOR TECHNOLOGY
REACTORS
SAMPLING
SHIPS
STAINLESS STEELS
TEMPERATURE
THERMAL NEUTRONS
TUBES
VOLUME
WATER
WATER COOLANT