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MFTF sensor verification computer program

Description: The design, requirements document and implementation of the MFE Sensor Verification System were accomplished by the Measurement Engineering Section (MES), a group which provides instrumentation for the MFTF magnet diagnostics. The sensors, installed on and around the magnets and solenoids, housed in a vacuum chamber, will supply information about the temperature, strain, pressure, liquid helium level and magnet voltage to the facility operator for evaluation. As the sensors are installed, recor… more
Date: November 9, 1984
Creator: Chow, H. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Production test IP-543-A effluent sampling -- overbore tube. Final report

Description: It had been postulated that the increased film area of a charged overbore tube would be counterbalanced by the lower temperature fuel surface and decreased flux so that the radioisotope content of the effluent would be the same as that from a normal tube. In order to confirm or deny the postulate, Tube 3267-C was equipped with an effluent sample line under the provisions of PT-IP-543-A. Sampling and analytical work began in mid-April and continued through November, 1963. Effluent samples obtain… more
Date: January 9, 1964
Creator: Geier, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of the PLTEMP code flow instability predictions with measurements made with electrically heated channels for the advanced test reactor.

Description: When the University of Missouri Research Reactor (MURR) was designed in the 1960s the potential for fuel element burnout by a phenomenon referred to at that time as 'autocatalytic vapor binding' was of serious concern. This type of burnout was observed to occur at power levels considerably lower than those that were known to cause critical heat flux. The conversion of the MURR from HEU fuel to LEU fuel will probably require significant design changes, such as changes in coolant channel thicknes… more
Date: June 9, 2011
Creator: Feldman, E. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Report on sodium compatibility of advanced structural materials.

Description: This report provides an update on the evaluation of sodium compatibility of advanced structural materials. The report is a deliverable (level 3) in FY11 (M3A11AN04030403), under the Work Package A-11AN040304, 'Sodium Compatibility of Advanced Structural Materials' performed by Argonne National Laboratory (ANL), as part of Advanced Structural Materials Program for the Advanced Reactor Concepts. This work package supports the advanced structural materials development by providing corrosion and te… more
Date: July 9, 2012
Creator: Li, M.; Natesan, K.; Momozaki, Y.; Rink, D.L.; Soppet, W.K. & Listwan, J.T. (Nuclear Engineering Division)
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Process System Hydraulics

Description: An analysis of hydraulic characteristics of the reactor plenum and the geometry of the permanent tube slots indicates the effect of the plenum pressure gradient on flow is substantially less than has been used previously to determine process water flows from cumulative fuel assembly resistances. This report details results of that study.
Date: August 9, 2002
Creator: Bland, C.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

A PROPOSAL FOR THE CONTROLLED RELEASE OF STORED ENERGY IN THE MTR REFLECTOR GRAPHITE

Description: A study of the stored energy buildup in the MTR reflector graphite and a program of controlled energy release is presented. Calculations, based on measurements of samples from the pebble zone show that an inadvertent spontaneous stored energy release would cause a temperature rise of 90 deg F in the pebble zone. The maximum transient structure temperatures resulting from a worst credible accidental release of energy would be less than allowable at present (except for possible damage to neutron … more
Date: December 9, 1959
Creator: Fast, E.; Smith, E.O. & Ford, J.D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Trip Rerport Organic Reactor Collant Survey

Description: A preliminary report has shown the potential importance of organic reactor coolants to Hanford technology. The salient points are complete avoidance of corrosion problems and accomplishment of DPR performance with low pressure technique. The recommendation of the report that loop tests be made at Hanford is to be acted upon by Recirculation Technology Unit as soon as organic coolant material is received. To insure starting this experimental work fully abreast of the information available, a tri… more
Date: July 9, 1956
Creator: Atwood, J. K.; Cook, M. W. & Hanthorn, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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