PM-1 NUCLEAR POWER PLANT PROGRAM. Quarterly Progress Report No. 4 for December 1, 1959 to February 29, 1960 [electronic resource]

The objective of the contract is the design, development, fabrication, installation, and initial testing and operation of a prepackaged air- transportable pressurized water reactor nuclear power plant, the PM-I. The specified output is 1 Mw(e) and 7 million Btu/hr of heat. The plant is to be operati...

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Bibliographic Details
Online Access: Online Access (via OSTI)
Format: Government Document Electronic eBook
Language:English
Published: Washington, D.C. : Oak Ridge, Tenn. : U.S. Atomic Energy Commission ; distributed by the Office of Scientific and Technical Information, U.S. Department of Energy, 1960.
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MARC

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049 |a GDWR 
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245 0 0 |a PM-1 NUCLEAR POWER PLANT PROGRAM. Quarterly Progress Report No. 4 for December 1, 1959 to February 29, 1960  |h [electronic resource] 
260 |a Washington, D.C. :  |b U.S. Atomic Energy Commission ;  |a Oak Ridge, Tenn. :  |b distributed by the Office of Scientific and Technical Information, U.S. Department of Energy,  |c 1960. 
300 |a Pages: 307 :  |b digital, PDF file. 
336 |a text  |b txt  |2 rdacontent. 
337 |a computer  |b c  |2 rdamedia. 
338 |a online resource  |b cr  |2 rdacarrier. 
500 |a Published through SciTech Connect. 
500 |a 04/01/1960. 
500 |a "mnd-m-1815" 
500 |a Smith, E H. 
500 |a Martin Co. Nuclear Div., Baltimore, MD. 
520 3 |a The objective of the contract is the design, development, fabrication, installation, and initial testing and operation of a prepackaged air- transportable pressurized water reactor nuclear power plant, the PM-I. 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 quarter were the near-completion of the final design and preparation of specifications for plant components. The entire power plant has been divided, for final design purposes, into 37 subsystems. The status of work on each subsystem at the close of the period is reported. A revised summary of design parameters is given, with flow diagrams of the primary and secondary systems. The final design work will be concluded early in the next report period. Systems development work included full-scale structural testing of a test package, preparation for a loading demonstration and testing of the air-steam condenser model. Reactor development work included: (1) Final preparations for the flexible zero-power test (PMZ-1) program. (2) Final preparations for the revised fuel element irradiation test program. (3) Continuation of reactor flow tests. One-fourth-scale model flow tests were completed and preparations for bundle flow and full-scale tests were continued. (4) Further work on the heat transfer test program, including fabrication, installation and testing of test section STTS-3, and fabrication of test sections STTS-4 and SETCH-2. (5) Final design and fabrication of the prototype magnetic jack-type control rod actuators. Work continued on study of control rod materials, with emphasis on fabrication techniques and stabilization of rare earth oxides. (For preceding period see MND-M-1814.). (auth) 
536 |b AT(30-1)-2345. 
650 7 |a Aircraft.  |2 local. 
650 7 |a Condensers.  |2 local. 
650 7 |a Control Elements.  |2 local. 
650 7 |a Control Systems.  |2 local. 
650 7 |a Environment.  |2 local. 
650 7 |a Fabrication.  |2 local. 
650 7 |a Fluid Flow.  |2 local. 
650 7 |a Fuel Elements.  |2 local. 
650 7 |a Heat Transfer.  |2 local. 
650 7 |a Heating.  |2 local. 
650 7 |a Irradiation.  |2 local. 
650 7 |a Liquid Flow.  |2 local. 
650 7 |a Machine Parts.  |2 local. 
650 7 |a Operation.  |2 local. 
650 7 |a Oxides.  |2 local. 
650 7 |a Planning.  |2 local. 
650 7 |a Pm-1.  |2 local. 
650 7 |a Power.  |2 local. 
650 7 |a Power Plants.  |2 local. 
650 7 |a Pressure.  |2 local. 
650 7 |a Rare Earths.  |2 local. 
650 7 |a Reactor Fueling.  |2 local. 
650 7 |a Reactors.  |2 local. 
650 7 |a Remote Handling.  |2 local. 
650 7 |a Rods.  |2 local. 
650 7 |a Stability.  |2 local. 
650 7 |a Standards.  |2 local. 
650 7 |a Testing.  |2 local. 
650 7 |a Transport.  |2 local. 
650 7 |a Uses.  |2 local. 
650 7 |a Water Coolant.  |2 local. 
650 7 |a Water Moderator.  |2 local. 
650 7 |a Reactor Technology.  |2 edbsc. 
710 2 |a U.S. Atomic Energy Commission.  |4 spn. 
710 1 |a United States.  |b Department of Energy.  |b Office of Scientific and Technical Information.  |4 dst. 
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