Published: 1983-09-09

Articles

Development and Application of Computer Codes for Multidimensional Thermalhydraulic Analysis of Nuclear Reactor Components

M.B. Carver

3-27

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The Advantages and Limitations of the Sets Method

John H. Mahaffy

28-39

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RELAP5/MOD2: For PWR Transient Analysis

V.H. Ransom

40-60

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Progress in Modelling Separated Flow Effects in the Refilling of Horizontal Heated Channels

K.H. Ardron, F.W. Barclay, B.N. Hanna, J. Mallory, B.H. Mconald, D. Scarth, C.B. So

61-70

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Neutronics Calculations in Large Symbiotic Spallation-Fission Reactor-Assemblies

W. Scherer

84-96

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Anomalies in One-Dimensional Thermal Hydraulics Calculations

E.M. Gelbard, J.R. Hofmann

71-83

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Variational Methods in Steady Sta.te Diffusion Problems

Clarence E. Lee, Wesley C.P. Fan, Robert L. Bratton

97-120

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Recent Developments in the ROCS/MC Code for Retrieving Local Power Information in Coarse-Mesh Reactor Analysis

S.F. Grill, A. Jonsson, M.W. Crump

121-149

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A Critical Review of Homogenization Techniques in Reactor Lattices

P. Benoist

150-154

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A Simple Stability Criterion for CANDU Figure-of-Eight Flow Oscillations

P. Gulshani, N. Spinks

155-175

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Two Dimensional Analysis of Conduction-Controlled Rewetting with Internal Heat Generation

Cheng-Hsing Hsu, Ching-Chang Chieng

176-200

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Verification of SOPHT for Parallel Channel Flow Stability

D.J. Richards, J.A. Lorenc, W.I. Midvidy

201-225

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Turbulence Modeling of Thermal and Fluid Mixing i PWR's During High Pressure Coolant Injection Using COMMIX-1B

F.F. Chen, H.M. Domanus, W.T. Sha

226-248

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An Assessment of Finite Element Synthesis Model Using 3D FEM

V. Jagannathan, B.P. Rastogi

249-268

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Rational Mapping (RAM) of In-Core Data

R.A. Banalumi, N. Kherani

269-282

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Possible Use of Measurements to Ament Cross Section Tables (PUMA)

N. Kherani, R.A. Banalumi

283-306

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On the Theory of Interface Flux Nodal Method

Yung-An Chao, Chang-An Suo, John Penkrot

307-326

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Nested Element Method in Multidimensional Neutron Diffusion Calculations

D.V. Altiparmakov

327-347

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Numerical Analysis for Reflood Simulation Based on a Mechanistic, Best-Estimate, Approach by KREWET Code

Moon-Hyun Chun, Eun-Soo Jeong

513-530

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ASSERT and COBRA Predictions of Flow Distribution in Vertical Bundles

A. Tahir, M.B. Carver

371-387

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A Numerical Technique for Reactor Subchannel Analysis

Hassan E.S. Fath

388-407

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Subchannel Flow Distributions in CANDU Fuel Channels Following Deformations

O. Akalin, C. Blahnik, D.B. Reeves, J.H.K. Lau

408-415

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The Assessment of Tornado Missile Hazard to Nuclear Power Plants

Julius Goodman, J.E. Koch

416-429

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Accuracy and Efficiency of Monte Carlo Method

Julius Goodman

430-441

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A Methodology for Reviewing Probabilistic Risk Assessments

Stephen L. Derby

442-457

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Learning Curve Estimation Techniques for Nuclear Industry

Jussi K. Vaurio

458-470

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Radial Heat Transfer from Fuel to Moderator During LOCAs for CANDU-PHW Reactors

J.G. Hildebrandt, C. So, G.E. Gillespie, G. MacLean

471-491

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The Effect of Header Void Distributions on CANDU Fuel Channel Flow Following Inlet Header Stratification

William C. Bowman, Jerry M. Hopwood

492-512

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Numerical Simulation of Two-Phase Flow in Horizontal Interconnected Subchannels

M. Shoukri, A. Tahir, M.B. Carver

348-370

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A Two Unequal Fluids (TUF) Model for Thermal-Hydraulics Analysis

R.A. Bonalumi, W. Liu, W.W. Yousef, J. Pascoe

531-554

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COMMIX-1A Analysis of Fluid and Thermal Mixing in a Model Cold Leg and Downcomer of a PWR

B.C-J. Chen, B.K. Cha, C.C. Miao, W.T. Sha, J.H. Kim, K.H. Sun

555-577

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