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1 Introduction
Pages 10-22

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From page 10...
... The reactor vessel contained only the molten salt filet and the graphite moderator. Heat from the fission reactions elevated the iTo sustain a critical chain reaction in an assembly of fissile material, each nuclear fission event produces, for every thermalized neutron captured, approximately two energetic neutrons (which, with moderation and loss mechanisms, result in approximately one thermalized neutron to participate in a subsequent fission event)
From page 11...
... The fuel salts were circulated in a loop containing the reactor vessel, a heat exchanger, and a pump. The coolant salts circulated in a loop consisting of the heat exchanger, a separate pump, and a radiator, from which the heat was dissipated to the air (up a stack)
From page 13...
... 13 o X ~ Ci ~ cat ~ ~ m 4:: 0 ~ ~ i> a: ~ m U,Y 0 ~ :5 m ~ ~ y z ° ~ · ~ ~ 0 0 hi ~ ok\ ° O° .
From page 15...
... In October 1996, the vent piping was at an overpressure of approximately one atmosphere, due to F2 and UFO gases, with solid plugs of uranium fluoride deposits inferred from pressure differences in piping runs leading from the drain tanks to the ACE at the end of the vent line. The facility's two immediate hazards gas buildup and solid uranium fluoride deposits are being addressed by work in progress at ORNL.
From page 16...
... act, , 1~ ' :~1 1 ~ 1 1 , I I ,, ,, 1 1 FUEL SALT SYSTEM ~ FILL AND DRAIN LINE —TANK FILL LINE ~ INSPECTION, SAMPLER, AND / LEVEL PROBE AGGESS STEAM DROME I CORRUGATED FLEXIBLE HOSE STEAM FIEFS BAYONET SUPPORT PLATE HANGER GABLE _~` INSTRUMENT THIMBLE ~ FUEL SALT DRAIN TANK ,. ~ TANK FILL LINE 11 ~ —THIMBLE POSITIONING RINGS FIGURE 1.4 Sketch of an MSRE fuel drain tank, made of a nickel alloy (Hastelloy N)
From page 17...
... 17 o lo lo / I ~ _ CUP 1 1 1 1 l 1 ~ _ Of'' ;1 1 \1 / I F / 1 1 /'/ 1 1 ~ I ~ \ _ _~ ~ ~ .
From page 18...
... , following the Comprehensive Environmental Response, Compensation, and Liability Act (CERCLA) regulatory process, is exploring technically feasible operations designed to reduce the hazard posed by the salts in these tanks.
From page 19...
... These considerations are at a stage where relevant scientific and technical information now under development on the identified alternatives will provide input to a future binding regulatory decision on the particular remediation option selected for the MSRE salts. This decision involves selection of the remediation alternative considered to be the best, as judged against all CERCLA criteria.2 ROLE OF THE NATIONAL RESEARCH COUNCIL At the request of DOE, the National Research Council (NRC)
From page 20...
... Chemical and technical aspects of the problem, including the current state of the molten salt reactor fuel and flush salts, tanks, and related equipment (e.g., associated tubing, valves, and sensors) , have been discussed and summarized in Peretz (1996c)
From page 22...
... The final chapter (Chapter 9) contains a summary discussion with commentary on the waste management strategy appropriate for the molten salt cleanup efforts.


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