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IBM 650 COMPUTER--PROGRAM NUMBER 655 COLLATION OF ROC CODE OUTPUT

Description: Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point. Program details are given including 650 input and output formats, operating instructions, and guides. (auth)
Date: December 19, 1958
Creator: Stueck, C.J.
Partner: UNT Libraries Government Documents Department

SN5001-AN IBM-650 CODE FOR STEADY-STATE THERMAL EVALUATION OF AN INSTRUMENTED MULTIFUEL-PLATE SUBASSEMBLY

Description: An IBM-650 computer program, SN5001, for the calculation of steady-state thermal conditions in the fuel plates and coolant of an instrumented multi-fuel- plate subassembly is described. The program is applicable for subcooled or bulk boiling coolant conditions and surface conditions of heating, local boiling, and film boilimg, and can be used for data reduction or design. The derivation and a list of the heat conduction and coolant enthalpy equations and a description of the code sufficient for its use are contained. (auth)
Date: April 1, 1960
Creator: Arbtin, E. & Westphal, R.B.
Partner: UNT Libraries Government Documents Department

ATBAC CHECK CALCULATION ON THE IBM 650, PROGRAM NO. 303

Description: This program, using the lBM 650 electronic data processing machine, is used primarily as a tool in order to prepare input data for an lBM 704 code ATBAC. The code calculates steady state thermal characteris tics of a plate type fuel element for both a nominal and adverse chanael. (auth)
Date: March 13, 1959
Creator: Beretsky, I. & Oby, P.V.
Partner: UNT Libraries Government Documents Department

Solutions of Systems of Differential Equations

Description: FOLDER is a routine whose purpose is to solve a system of linear differential equations on the IBM 650 computer which is equipped with index accumulators and floating-point hardware. A system of K n/sup th/-order differential equations which is represented by a system of K x n first-order differential equations and coded in a prescribed manner is solved numerically by the methods of Milne and/or Runge-Kutta. Flexible operating modes are made possible by the user's designtion of parameters. Output data and format are under complete control of the user. (auth)
Date: June 1, 1959
Creator: Clay, R. L.
Partner: UNT Libraries Government Documents Department

NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

Description: The Early Program is designed to compute the peak power and total energy release vhich will occur in a reactor due to a step increase of reactivity. These excursions may be terminated by one of several automatic shutoff mechanisms caused by the power excursion itself. The calculation assumes no thermodynanaic delays and assumes void formation is due to heat conduction from the cladding to the moderator. (W.D.M.)
Date: February 26, 1959
Creator: Reiback, E.M. & Stueck, C.J.
Partner: UNT Libraries Government Documents Department

A BOILING WATER ANALYSIS CODE ON THE IBM-650--ABWAC-MNC PROGRAM NO. 302

Description: A method was developed for using an IBM-650 data processing machine to obtain detailed information concerning thermal and hydraulic conditions within a platetype reactor channel when the coolant in the channel is present in both vapor and liquid phases. (auth)
Date: March 10, 1959
Creator: Beretsky, I. & Pacine, S.
Partner: UNT Libraries Government Documents Department

REFLECTOR AND PRESSURE VESSEL COOLING AND THERMAL STRESS ANALYSIS ON THE IBM 650

Description: S>These programs are intended to:ssist in establishing reflector cooling requirements, as well as thermal stresses in the reflectors and pressure vessel. The main program (304-Rec I) establishes required velocities between reflectors as a function of geometry, heat generation rates, material and fluid properties, and allowable surface temperature. This is done by iterating on velocities for successive water gaps. When required velocities have been established, corresponding thermal stresses are calculated. Rec II (301) and Prev I (301A) are supplement programs. Rec II is utilized for establishing surface temperatures of a reflector as a function of velocities, geometry, heat generation rates, and matenial and fluid properties. It handles only one reflector per case. This program also calculates thermal stresses in the reflector. Prev I is intended for calculations concerning a pressure vessel, perfectly insulated at the outer surface. It calculates surface temperature and thermal stresses in the vessel as a function of velocity, geometry, heat generation rates, and matenial and fluid properties. All calculations are performed at the midplane, where maximum heat generation rates occur. (auth)
Date: March 26, 1959
Creator: Love, J.D. & Caton, R.L.
Partner: UNT Libraries Government Documents Department

THERMAL ANALYSIS ON THE IBM 650. LOVELY-I, PROGRAM NO. 55

Description: A program is given for the establishment of flow requirements of a tailored flow core. It is capable of handling either one- or two-pass cores, with flow direction optional in each pass, and a reflector coolant flow in parallel with elther pass. The various configurations which may be investigated are illustrated. Although the program is specifically intended for APPRtype elements, flows may be established for any set of dimensions snd pressure and temperature conditions and corresponding to any desired maximum allowable surface temperature. It hes expected that, due to pressure drop considerations, for two- pass flow all control rods will be in the same pass. Calculated results include flow requirements of each indivldual type of element, as well as total internal flow, lattice flow, and finally the total required flow for each pass. Calculation of the maximum ratio of operating to burnout heat flux and maximum internal temperature is optional. (auth)
Date: November 26, 1958
Creator: Love, J.D. & Stuack, C.J.
Partner: UNT Libraries Government Documents Department

SO131--AN IBM-650 CODE TO SOLVE PRESSURE AND THERMAL STRESS PROBLEMS IN CORE SUBASSEMBLY PLATES

Description: In the design of nuclear reactor core subassemblies, a stress analysis is often made of a subassembly whose plates differ in geometry, in reactor coolant pressure loading, and in temperature distribution. Bettis code S0131 was developed for the IBM-650 computer to assess the adequacy of the subassembly design and to assist in determining acceptable manufacturing tolerances. The output of the code gives redundant weld reactions, deformations, and stresses in the individual plates. (auth)
Date: August 1, 1959
Creator: Friedrich, C.M.
Partner: UNT Libraries Government Documents Department

NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

Description: The early program is designed to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity. The calculation assumes no thermodynamic delays and assumes void formation is due to heat conduction from the cladding to the moderator. For periods in the 1 to 10 msec. range, the calculation yields results which are in excellent agreement with SPERT experimental results. (W.D.M.)
Date: February 26, 1959
Creator: Stueck, C.J. & Reiback, E.M.
Partner: UNT Libraries Government Documents Department

PRIMARY SHIELDING CALCULATIONS ON THE IBM 650 (ROC CODES)

Description: Four programs written for the IBM 650 to calculate the gamma dose rates in the primary shielding of thermal reactors are described. Their functions are outlined as follows: Program 651-calculates the core attenuation coefficient and equivalent core gamma volumetric source values for a specific core. Program 652- calculates the activation gamma source data in the shield and prepares tabular data in machine storage for Programs 653 and 654. Program 653- calculates the gamma dose rates in the shield due to gammas arising from activation of shield materials. Program 654calculates the gamma dose rates in the shield due to gammas arising in the core. Gamma photo source values are obtained on the basis of two group neutron flux distributions throughout the reactor core and shield. (W.D.M.)
Date: October 15, 1958
Creator: Rosen, S.S.; Oby, P.V. & Caton, R.L.
Partner: UNT Libraries Government Documents Department