Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux (open access)

Final Report: Investigation of Boiling Flow Regimes and Critical Heat Flux

From abstract: A program to investigate the mechanism of the critical heat flux condition from the standpoint of flow regimes has been initiated at Dynatech for the AEC. This report covers the work done on this investigation in the first year.
Date: March 1, 1965
Creator: Suo, M.; Bergles, Arthur E.; Doyle, Edward F.; Clawson, L. & Goldberg, P.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1967

Areas of work reported include: general radiation effects; toxicity of radioelements; combating detrimental effects of radiation; studies at the molecular and cellular level; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date: March 1, 1967
Creator: Fawcett, S. L.
System: The UNT Digital Library
Evaluation of Irradiated OMRE Fuel Elements First Core Loading (open access)

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date: March 1, 1960
Creator: Walter, J. H.; Leirich, J. F. & Calkins, G. D.
System: The UNT Digital Library
Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1969 (open access)

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: February 1969

Progress is updated for projects related mostly to biological and ecological radiation effects.
Date: March 1, 1969
Creator: unknown
System: The UNT Digital Library
Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program (open access)

Development of High-Temperature Electrical Ground Test Heaters for the SNAP 10A Program

Introduction: The development and qualification of the system acceptance test heaters and the reactor simulator heater are described in this progress report.
Date: March 1, 1965
Creator: Blevitt, R.; Paine, G. & Sudar, S.
System: The UNT Digital Library
KEWB Program Quarterly Progress Report: July-September 1956 (open access)

KEWB Program Quarterly Progress Report: July-September 1956

From abstract: The response of the reactor to forced oscillations has been investigated with the pile oscillator technique and the data are presently being analyzed.
Date: March 1, 1957
Creator: North American Aviation. Atomics International Division. Kinetic Experiments on Water Boilers Program.
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 2, March-August 1963

From summary: The full 140 element loading of the core was completed on October 10, 1962. At this point, critical operation was begun for operator training and post-critical testing purposes.
Date: March 1, 1964
Creator: Darley, D. K.
System: The UNT Digital Library
Multi-Channel Boiling Stability for Sodium Graphite Reactors (open access)

Multi-Channel Boiling Stability for Sodium Graphite Reactors

Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date: March 1, 1962
Creator: Cappel, H. H.
System: The UNT Digital Library
Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors (open access)

Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors

This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date: March 1, 1962
Creator: Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
System: The UNT Digital Library
EVESR Nuclear Superheat Fuel Development Project: Third Quarterly Report, December 1962-February 1963 (open access)

EVESR Nuclear Superheat Fuel Development Project: Third Quarterly Report, December 1962-February 1963

Quarterly report describing progress on the EVESR Nuclear Superheat Fuel Development Project.
Date: March 1, 1963
Creator: Pennington, R. T.
System: The UNT Digital Library
Halogen Collector Test Program (open access)

Halogen Collector Test Program

Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date: March 1, 1960
Creator: Arthur D. Little, Inc.
System: The UNT Digital Library