HEAVY WATER MODERATED POWER REACTORS. Progress Report for January 1960

Technical Report · Tue Mar 01 04:00:00 EST 1960

DOI:https://doi.org/10.2172/4143374· OSTI ID:4143374

Isakoff, L. comp.

Approximately one-quarter of the construction and 85% of the firm design of the Heavy jWater Components Test Reactor (HWCTR) were complete at the end of January 1960. Safeguards analyses of the liquid-D/sub 2/O-cooled loop of the HWCTR showed that none of the accidents considered to date have serious potential. Exploratory tests of the a device for quenching the steam that would be generated in the boiling-D/sub 2/O- cooled loop of the HWCTR showed that a quencher could be designed to operat satisfactorily without excessive accompanying noise or vibration. Two Zircaloy-=cald tubes of crused, fused uranium oxide were cold swaged to a density of greater than 90% of theoretical. Several other cold-swagged oxide tubes clad with stainless steel were fabricated for irradiation specimens. Mechanical, hydraulic pressure, thermal-and pressure- cycling tests of tubular metallurgical joints between Zircaloy and stainless steel continued to show excellent properties. (For preceding period see DP-455.) (auth)

• Research Organization: Du Pont de Memours (E.I.) & Co. Atomic Energy Div., Wilmington, Del.
• NSA Number: NSA-14-013470
• OSTI ID: 4143374
• Report Number(s): DP-465
• Country of Publication: United States
• Language: English

Related Subjects

ACCIDENTS
BOILING
COOLANT LOOPS
DENSITY
FABRICATION
FUEL CANS
FUEL ELEMENTS
HEAVY WATER COOLANT
HEAVY WATER MODERATOR
HYDRAULICS
JOINTS
MECHANICAL PROPERTIES
POWER PLANTS
PRESSURE
REACTOR SAFETY
REACTOR TECHNOLOGY
REACTORS
STAINLESS STEELS
STEAM
TESTING
URANIUM OXIDES
VIBRATIONS
ZIRCALOY