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Reactivity of Substitution Elements

Description: A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date: unknown
Creator: Murray, R. L., Dr.
Partner: UNT Libraries Government Documents Department
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Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets

Description: In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date: unknown
Creator: Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Partner: UNT Libraries Government Documents Department
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Structural Testing of SM-2 Fuel Elements

Description: Ability of the originally designed SM-2 stainless steel fuel elements, of both tungsten inert gas (TIG) and electrical resistance welded construction, to withstand static transverse pressure gradients of normal reactor operation was investigated
Date: unknown
Creator: Coleman, F. G., Jr. & Herbert, R. J.
Partner: UNT Libraries Government Documents Department
open access

SM-1 Research and Development Quarterly Report : April 1 to June 30, 1960

Description: This report covers research conducted at the SM-1 and highlights progress made in plant water chemistry and health physics practices and progress on individual tasks and test are reported
Date: unknown
Creator: Bergman, C. A.
Partner: UNT Libraries Government Documents Department
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Nuclear Analysis of Various Spert-III Critical Experiments

Description: The calculational models employed in the nuclear analysis of the SM-2 were applied to various critical experiments performed upon the SPERT-III core
Date: unknown
Creator: Paluszkiewica, S.
Partner: UNT Libraries Government Documents Department
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Preliminary Stress and Fatigue Analysis of the SM-1 Primary System

Description: A preliminary analysis of the SM-1 primary system showed it was safe from strain cycling damage with possible exception of steam generator tube sheet and primary pump casing
Date: unknown
Creator: Chittum, R. A.; Knipe, R. K. & McLaughlin, D. W.
Partner: UNT Libraries Government Documents Department
open access

Bobcat (Program No. 56) Code Preparation Analysis on the IBM-650

Description: This report contains a description of the BOBCAT code, (Program 56), programmed for the IBM-650. The code greatly facilitates the nuclear analysis of APPR-type cores by performing many of the routine calculations necessary to obtain input to various IBM-650 and IBM-704 codes.
Date: unknown
Creator: Bobe, P. E. & Caton, R. L.
Partner: UNT Libraries Government Documents Department
open access

Summary Nuclear Calculations for the SM-2 Core I

Description: This report presents the results of a limited analysis of the Extended SM-2 Critical Experiments. A review of the analytical models is presented to ascertain the accuracy of the reactivity calculations for the reference SM-2 Core I
Date: unknown
Creator: Fried, B. E.; Beam, R. H. & Bobe, P. E.
Partner: UNT Libraries Government Documents Department
open access

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
open access

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
open access

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
open access

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
open access

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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