Open AccessPRELIMINARY DESIGN REPORT FOR THE NMSR PRESSURIZED WATER LOOP AT ORR
Author(s) -
I.T. Dudley,
D.B. Trauger,
H.C. Savage
Publication year - 1958
Language(s) - English
Resource type - Reports
DOI - 10.2172/4199724
Subject(s) - loop (graph theory) , heat exchanger , nuclear engineering , neutron flux , pressurized water reactor , flux (metallurgy) , space velocity , materials science , thermal , research reactor , water cooled , chemistry , neutron , mechanical engineering , water cooling , nuclear physics , engineering , physics , thermodynamics , metallurgy , mathematics , biochemistry , combinatorics , selectivity , catalysis
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