HEAVY WATER POWER REACTOR PROGRAM. Monthly Progress Report, March 1961

Technical Report · Tue Oct 31 00:00:00 EST 1961

OSTI ID:4027555

S>Research and Development. A four-tube machine was proposed for use as the CANDU refueling machine. The ball valve appears to be satisfactory for use in the adapter valve assembly for closure of pressure tube and fittings during charging and discharging operations. Operation and performance are reported for Task X loop run. In investigations of the cause of failure of vibratory- compacted and swaged UO/sub 2/ tubes clad with Zircaloy-2, hydride formation was detscted on the inside surface of an inner sheath of an unfailed tube. The total and partial void coefficients of reactivity associated with removal of coolant from the PLATR 37-and UO/sub 2/ clusters were measured. Test results on the effect of in-pile local boiling on surface deposition of Zircaloy-2 clad fuel specimens indicate a linear relationship, independent of the heat transfer mode, between crud deposition and thermal neutron flux. Heavy Water Components Test Reactor. Tests of the refurbished prototype control-rod-drive assemblies at SRP gave satisfactory performance. The current status of the reactor and proposed modifications and testing are reviewed. Power Demonstration Program. Improved CVTR plant performance (conversion ratio and heat channel factors) can be obtained by reducing pressure tube and clad thicknesses. A new pressure tube wall thickness was established based on Reference Design II criteria, higher material properties, and different design temperatures and pressures. Preliminary tests on a moolfied three-baffle assembly indicate a heat leakage - 15% higher than from the Phase II studies, which is ascribed to non-concentric and imperfect baffles. Three series of Phase II heat leakage tests showed that the ball point gave effective sealing. Since Q/ delta T was found to vary linearly with the coolant temperature, the use of an average coolant temperature to calculate heat transferred from coolant to moderator is valid. To minimize heat losses, the moderator level must be kept below the top of the gas shroud. Effective mining flow ratss were measured for various fuel rod wrapping configurations. The contact resistance between UO/sub 2/ and Zircaloy-2 was determined for various heat fluxes. Irradiation samples revealed two differert types of columnar grains in UO/sub 2/. The control rod drive mechanism was modified to increase the lifting torque and to reduce control rod flutter. Measurements of the coolant void coefficient were made in process tubes at the center and edge of the core using degraded D/sub 2/. Other reactor measurements were also made, particularly neutron flux distributions. The current status of tasks under the ECNG/FWCNG program is reviewed. (D.L.C.)

• Research Organization: Savannah River Operations Office, AEC
• NSA Number: NSA-15-016717
• OSTI ID: 4027555
• Report Number(s): SRO-43
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-61
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
CANDU
CONTROL ELEMENTS
CVTR
DEPOSITS
DISTRIBUTION
FUEL CANS
HEAT TRANSFER
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
HWCTR
HYDRIDES
IRRADIATION
MEASURED VALUES
NEUTRON FLUX
PERFORMANCE
PLATR
REACTIVITY
REACTOR FUELING
REACTORS
RODS
SEALS
SERVOMECHANISMS
THICKNESS
URANIUM DIOXIDE
VALVES
ZIRCALOY