An In-Pile Loop Study of the Performance of Polyphenyl Reactor Coolants

Technical Report · Mon Sep 15 00:00:00 EDT 1958

DOI:https://doi.org/10.2172/4304037· OSTI ID:4304037

Bley, William N. ^[1]

---

1. North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.

An in-pile loop experiment was performed to evaluate several promising polyphenyl materials for use as reactor moderator coolants. Isopropyl diphenyl, diphenyl, a mixture of Santowax O and Santowax M, and Santowax R were circulated in an in-pile loop containing a uranium heater, at bulk fluid temperatures of 500 to 700°F and at fluid velocities of 10 to 20 ft/sec over the heat transfer surfaces. Heat fluxes ranged from 120,000 - 200,000 Btu/hr-ft². Peak reactor fluxes surrounding the in-pile assembly were 5 x 10¹³ thermal neutrons/cm²-sec, 1.2 x 10¹² fast neutrons/cm²-sec, and 0.6 watt/gm gamma heating. No significant differences between the materials irradiated were apparent insofar as radiation stability, heat transfer properties, and corrosion were concerned. Radiation decomposition rates were slightly greater than those measured in previous work. However, the decomposition rates were not unreasonable. Coolant activation and corrosion were negligible. Heat transfer characteristics were not adversely affected by physical property changes or high radiation fields.

• Research Organization: North American Aviation, Inc., Canoga Park, CA (United States). Atomics International Div.
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(11-1)-GEN-8
• NSA Number: NSA-13-000446
• OSTI ID: 4304037
• Report Number(s): NAA-SR--2470
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
ACTIVATION
CONTAMINATION
CORROSION
DECOMPOSITION
FAST NEUTRONS
FLUID FLOW
GAMMA RADIATION
HEAT TRANSFER
HIGH TEMPERATURE
IN PILE LOOPS
IRRADIATION
MATERIALS TESTING
MEASURED VALUES
NEUTRON FLUX
ORGANIC COOLANT
ORGANIC MODERATOR
POLYPHENYLS
RADIATION CHEMISTRY
RADIATION EFFECTS
RADIOLYSIS
REACTORS
SANTOWAX
STABILITY
SURFACES
THERMAL NEUTRONS
VELOCITY