ARMY PWR SUPPORT AND DEVELOPMENT PROGRAM. SECOND HALF-YEAR SUMMARY REPORT, APRIL 1, 1961-SEPTEMBER 30, 1961

Technical Report · Fri Dec 15 00:00:00 EST 1961

DOI:https://doi.org/10.2172/4787273· OSTI ID:4787273

Results of a study of radiation damage in SM-1 reactor vessel indicated that replacement of the vessel is possible but impractical because of health physics problems. An evaluation of PH steel components revealed that 17-4 PH steel was used for several years in control rod drives without incident. A specification for 17-4 PH procurement was developed. Data and information concerning the performance of SM-1 Core I, SM-1 Core I rearranged and spiked, SM- 1 Core H, PM-2A Core I, and SM-1A Core I, are presented. Developments on replacement cores are also reported along with results of primary system performance analysis. A study of methods for improved activity control in primary systems was continued. Resulting data from an analysis of reactor pressure vessels during operating life are included, (J.R.D.)

• Research Organization: Alco Products Inc., Schenectady, N.Y.
• DOE Contract Number: AT(30-1)-2639
• NSA Number: NSA-16-012728
• OSTI ID: 4787273
• Report Number(s): APAE-108
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-62
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
CONTAMINATION
CONTROL
CONTROL ELEMENTS
COOLANT LOOPS
EFFICIENCY
FABRICATION
FAILURES
HEAT TRANSFER
MACHINE PARTS
MAINTENANCE
MATERIALS TESTING
MECHANICAL PROPERTIES
MECHANICAL STRUCTURES
MONITORING
MOTORS
NEUTRON FLUX
PERFORMANCE
POWER PLANTS
PRESSURE
PRESSURE VESSELS
PWR
RADIATION EFFECTS
RADIATION PROTECTION
RADIOACTIVITY
REACTIVITY
REACTOR CORE
RODS
SERVOMECHANISMS
SM-1
SM-1A
STEELS
TEMPERATURE