398 results on '"O CODES"'
Search Results
302. Shielding analysis of the retrievable surface storage facility
303. Bound states of one nucleon in a Woods--Saxon well from a variational method
304. Method for generating a control rod program for boiling water reactors
305. Calculated radiation properties of spent plutonium fuels
306. Nuclear optical model code for small computers.
307. METHODS FOR STUDYING FUEL MANAGEMENT IN ADVANCED GAS COOLED REACTORS.
308. MIXED-OXIDE FUEL PIN PERFORMANCE ANALYSIS USING THE OLYMPUS COMPUTER CODE.
309. OXIDE4
310. In-bore diagnostic and modeling of an electrothermal plasma launcher
311. A validation comparison of SHIELD system decay heat calculations to benchmark quality experiments
312. OPTIM: Computer program to generate a vertical profile which minimizes aircraft fuel burn or direct operating cost. User's guide
313. Applications of energy release rate techniques to part-through cracks in plates and cylinders. Volume 1. ORMGEN-3D: a finite element mesh generator for 3-dimensional crack geometries
314. OZMA: a code to calculate resonance reaction rates in reactor lattices using resonance profile tabulations
315. User's guide to PSS and OPS. [In FORTRAN for PDP-10]
316. User's manual for OZIPM-4. Volume 2. Computer code. Final report
317. Procedures for applying city-specific EKMA. Final report
318. OREDIT: a fortran computer program to process Oak Ridge HSSR data
319. OTOCI: ORINC to COBRA interface. [BWR, PWR]
320. OMNI user guide for the Energy Information Administration
321. Automated response functions
322. Estimation methodology for energy supply from natural resources. Final report. [OPCON]
323. PC-based system for generating EKMA input files. Final report
324. Tentative user interface standard for ODEPACK
325. ODRIC: a one-dimensional linear resistive MHD code in cylindrical geometry
326. Optimization of induction motor efficiency: Volume 2, Single-phase induction motors: Final report
327. OKUMA apt postprocessor
328. The TN-24P PWR spent-fuel storage cask: Testing and analyses: Interim report
329. OCA-I, a code for calculating the behavior of flaws on the inner surface of a pressure vessel subjected to temperature and pressure transients
330. Summary of computer codes for radiological assessment
331. User's manual for OZIPM-4 (Ozone Isopleth Plotting with Optional Mechanisms). Volume 1. Final report
332. Applications of energy-release-rate techniques to part-through cracks in plates and cylinders. Volume 2. ORVIRT: a finite element program for energy release rate calculations for 2-dimensional and 3-dimensional crack models. [PWR; BWR]
333. ORBEOS: a spherical, fully multidimensional flux-corrected transport-hydrodynamics code
334. User's guide for 10 CFR 61 impact analysis codes. [INTRUDE; GRWATER; OPTIONS; INVERSI; INVERSW]
335. ORTCAL: a code for THTF heater rod thermocouple calibration. [PWR]
336. Otter 1. 0 users' guide
337. Screening of contamination potential and site cleanup at manufactured-gas plant and pole treatment sites: Final report
338. Modification of OCA-I for application to a reactor pressure vessel with cladding on the inner surface. [PWR]
339. Core-concrete interactions using molten steel with zirconium on a basaltic basemat: The SURC-4 experiment
340. Automobile sector forecasting model documentation. Final report. [Input, Initialize, Policy, Simulate, and Output]
341. Optimization of life prediction using uncertain data
342. Technical operating documentation: Regional Emissions Projection System (REPS). [For forecasting air pollution emissions]
343. OESYS: a simulation tool for non-conventional energy applications analysis. Theoretical and operational description with user documentation
344. Oasis code application to proposed Argonne National Laboratory cogeneration plant
345. ODDBALL: ORNL Developed Data Base Analyzing Lukasiewicz Language. [In PDP-10 FORTRAN]
346. Mathematical methods of analysis of linear models: a documentation of the Linear Ecosystem Analysis Package (LEAP)
347. High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety. Quarterly progress report, April 1, 1976--June 30, 1976
348. Numerical methods in hydrodynamic calculations
349. High-temperature gas-cooled reactor safety studies for the Division of Reactor Safety Research. Quarterly progress report, October 1, 1976--December 31, 1976
350. ORCOST II: a computer code for estimating the cost of power from steam-electric power plants
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