PRELIMINARY DESIGN REPORT FOR THE NMSR PRESSURIZED WATER LOOP AT ORR

Technical Report · Thu Oct 23 04:00:00 EDT 1958

DOI:https://doi.org/10.2172/4199724· OSTI ID:4199724

Dudley, I T; Trauger, D B; Savage, H W

The design criteria, description, flow diagrams, and some drawings of a pressurized water loop in which reactor operation conditions can be simulated are presented. The prirnary purpose of this test facility is irradiation testing of various versions of fuel elements for use in the Merchant Ship Reactor Program. The loop proper is designed for operation at 625 deg F and 2250 psi with a water flow rate of 90 gpm. Heat exchanger capacity is 150 kw at 300-F system water temperature. Loop construction is of 300 series stainless steels throughout. A by-pass purification system provides for continuous water chemistry control. Fuel pin specimens are to be irradiated in the space provided by two tubes, 1.5 II) x 24 in. long, of the "hairpin" type in positions A1 and A2 of the OHR core. The average unpertarbed neutron flux at this point in the reactor is estimated to be 5 x 10/sup 13/ thermal. (auth)

• Research Organization: Oak Ridge National Lab., Tenn.
• NSA Number: NSA-14-007869
• OSTI ID: 4199724
• Report Number(s): CF-58-10-21
• Country of Publication: United States
• Language: English

Related Subjects

BYPASS
CONTROL SYSTEMS
COOLANT LOOPS
DIAGRAMS
FLUID FLOW
FUEL CANS
FUEL ELEMENTS
HEAT EXCHANGERS
IMPURITIES
IRRADIATION
MATERIALS TESTING
NEUTRON FLUX
OPERATION
ORR
PHYSICS
PLANNING
POWER
PRESSURE
QUALITATIVE ANALYSIS
REACTOR CORE
REACTORS
SAVANNAH
SHIPS
SPACE
STAINLESS STEELS
TEMPERATURE
TESTING
THERMAL NEUTRONS
TUBES
WATER