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Determination of Maximum Permissible Irradiation on Type 3 (SM-2) Fuel Plates

Description: Two methods were used for predicting the maximum permissible burnup in Type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on U02 stainless steel dispersion fuel plates.
Date: unknown
Creator: Wilder, A. S. & Kelleman, R. W.
Partner: UNT Libraries Government Documents Department
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Economic Analysis of Replacement Cores for the SM and PM Type Reactors

Description: An economic analysis is presented for the fabrication of replacement cores for SM and PM type reactors, including analysis of various core types and core fabrication technologies
Date: unknown
Creator: Wilder, A. S.
Partner: UNT Libraries Government Documents Department
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Evaluation of Wire Scanner for SM-1

Description: This report presents and evaluates preliminary design concepts of a wire scanner for experimentally evaluating spatial variations of neutron flux in the SM-1 reactor core
Date: unknown
Creator: Kemp, S. N.
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart is derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation is based upon local thermal and hydraulic considerations of minimum element-to-element coolant channel clearances
Date: unknown
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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SM-1 Reactor Vessel Cover and Flange Stress Analysis

Description: This report presents results of a stress analysis of the cover and flange region of the SM-1 reactor vessel
Date: unknown
Creator: Sayre, M. F.
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the SM-1A Reactor Vessel

Description: This report presents the stress analysis performed on the SM-1A reactor vessel and cover as part of the Program for Engineering Support and Development of Army Pressurized Water Reactor Power Plants.
Date: unknown
Creator: McLaughlin, D. W.; Rowekamp, B. J.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
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Program For The Development of Plutonium Recycle For Use In Light Water Moderated Reactors : Seventh Quarterly Report October 1-December 31, 1962

Description: The objective of this program is the experimental determination of basic physical data and employment of these data to establish and confirm a theoretical model for predicting the long-term changes in isotopic composition and reactivity in plutonium-enriched, light-water-moderated reactors.
Date: December 31, 1962
Creator: Roskin, M. A.
Partner: UNT Libraries Government Documents Department
open access

Stress Analysis of the PM-2A Reactor Vessel

Description: This report presents the stress analysis performed on the PM-2A reactor vessel and cover.
Date: unknown
Creator: Rowekamp, B. J.; McLaughlin, D. W.; Chittum, R. A. & Aitken, C. C.
Partner: UNT Libraries Government Documents Department
open access

Startup and Initial Testing of SM-1 Core II with Special Components

Description: The report gives the loading operation for SM-1 Core II, results of startup physics measurements and fission product iodine monitoring in the primary coolant
Date: unknown
Creator: Moote, F. G. & Schrader, E. W.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Single and Dual Turbine-Generator Units for PL-3

Description: This report describes the investigation performed relative to the selection of a turbine-generator unit for the PL-3 portable nuclear power plant
Date: unknown
Creator: Prall, T. F.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Heat Rejection Systems for PL-3

Description: This report covers an investigation of heat rejection systems for use in the PL-3 nuclear power plant.
Date: unknown
Creator: Thurnau, C. J.
Partner: UNT Libraries Government Documents Department
open access

Spent Fuel Transfer, Storage and Shipment for PL-3

Description: In refueling developments studies performed on PL-3 Phase I design, several methods of fuel transfer, storage, and shipment were investigated.
Date: unknown
Creator: Hauenstein, G. C. & Pomeroy, D. L.
Partner: UNT Libraries Government Documents Department
open access

Comparison of Gaseous Waste Handling Systems for PL-3

Description: This report compares gaseous waste handling systems for direct and indirect boiling water and pressurized water reactors for PL-3 application
Date: unknown
Creator: Noble, J. H. & Duke, E. E.
Partner: UNT Libraries Government Documents Department
open access

Prelimiary Analysis of the Plutonium Recycle Program Reactor Shield

Description: It is the purpose of this report to present the preliminary analysis of the PRPR shield. The results reflect a considerable degree of conservatism because of uncertainties that were present in the preliminary estimates of neutron and gamma fluxes incident on the shield.
Date: December 22, 1956
Creator: Wood, D. V. & Weeks, J. L.
Partner: UNT Libraries Government Documents Department
open access

Development Program For Increased Output In The Garigliano Nuclear Reactor : Quarterly Progress Report No. 1 September-December, 1962

Description: Authorization from the U.S. Atomic Energy Commission has been received to begin Pressure Vessel Sample Irradiation and Data logging and Computer System of the Development Program for Increased Output in the Garigliano Nuclear Reactor. The work described herein was performed in the period of September 1 to December 31, 1962.
Date: January 2, 1963
Creator: Quinn, E. P.
Partner: UNT Libraries Government Documents Department
open access

General And Stress Corrosion Of High Nickel Alloys In Simulated Superheat Reactor Environment

Description: It is the purpose of this report to summarize the results of the evaluation program carried out to-date on the high nickel alloys Inconel, Incoloy and Hastelloy-X in the out-of-pile superheat facilities as part of Task E of the Atomic Energy Commission sponsored Superheat Program.
Date: January 1963
Creator: Pearl, W. L. & Gaul, G. G.
Partner: UNT Libraries Government Documents Department
open access

General And Stress Corrosion Of High Nickel Alloys In Simulated Superheat Reactor Environment

Description: It is the purpose of this report to summarize the results of the evaluation program carried out to-date on the high nickel alloys Inconel, Incoloy and Hastelloy-X in the out-of-pile superheat facilities as part of Task E of the Atomic Energy Commission sponsored Superheat Program.
Date: March 1963
Creator: Pearl, W. L. & Gaul, G. G.
Partner: UNT Libraries Government Documents Department
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