PM-1 NUCLEAR POWER PLANT PROGRAM 3RD QUARTERLY PROGRESS REPORT FOR SEPTEMBER 1 TO NOVEMBER 30, 1959

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

DOI:https://doi.org/10.2172/4150785· OSTI ID:4150785

Smith, E H; Sieg, J S

A description is presented of work on the design, development, fabrication, installation, and initial testing and operation of a prepackaged air- transportable pressurized water reactor nuclear power plant, the PM-1. The specified output is 1 Mw(e) and 7 million Btu/hr of heat. The plant is to be operational by March 1962. The principal efforts during the third quarter were the furthering of the final design and preparation of specifications for some longlead components. The entire power plant was divided, for final design purposes, into 37 subsystems. The status of work on each subsystem is reported. A revised summary of design parameters is given, with flow diagrams of the primary and secondary systems. The most significant changes were in core design details and in the packaging and housing plan. A scheme for integral housing using the shipping containers for structural components was dropped, except for the decontamination package. Systems development work included preparations for full-scale structural testing of a test package, completion of the survey of incore instrumentation techniques, completion of development work on the reactor control and instrumentation system, and further development of components for the steam generator, condenser, and turbine generator which are not available commercially. The conclusions of the in-core and control instrumentation work are summarized briefly. Reactor development work included: (1) Preparations for the flexible zero-power test (PMZ-1) program. (2) Preparations for the revised fuel element irradiation test program. 13) Continuation of reactor flow tests. (4) Further work on the heat transfer test program, including evaluation and reporting of the seven-tabe test section tests (SETCH-1) and design of a follow- up program and unit (SETCH-2). (5) Completion of the single-tube test section program (STTS-2) and design of the follow-up STTS-3 and STTS-4 programs. (6) Further work on the development and tssttng of magnetic jack-type control rod actuators. Core fabrication commenced with delivery of the first batoh of UO/sub 2/ and pilot runs of fuel element fabrication. Ultrasonic testtng of selected pilot run fuel tubes was conducted. Work continued on study of control rod materials, UO/sub 2/ recovery techniques, and boron analysis. (For preceding period see MND-M-1813.1 (auth)

• Research Organization: Martin Co. Nuclear Div., Baltimore, MD
• Sponsoring Organization: US Atomic Energy Commission (AEC)
• DOE Contract Number: AT(30-1)-2345
• NSA Number: NSA-14-017600
• OSTI ID: 4150785
• Report Number(s): MND-M-1814
• Resource Relation: Other Information: Orig. Receipt Date: 31-DEC-60
• Country of Publication: United States
• Language: English

Related Subjects

REACTOR TECHNOLOGY
BORON
BUILDINGS
CONDENSERS
CONTROL ELEMENTS
CONTROL SYSTEMS
DECONTAMINATION
DIAGRAMS
FABRICATION
FUEL ELEMENTS
GENERATORS
HEAT TRANSFER
INSTRUMENTS
IRRADIATION
LIQUID FLOW
MOTION
PLANNING
PM-1
POWER PLANTS
PRESSURE
REACTOR CORE
REACTORS
STEAM
TESTING
TRANSPORT
ULTRASONICS
URANIUM DIOXIDE
WATER COOLANT