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Volume 71

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Number 1

Table of Contents
Authors(Mario Dalle Donne, Ulrich Fischer, Marko Küchle, Leslie Cave, William E. Kastenberg, Maurizio Bottoni, Burkhardt Dorr, Christoph Homann, Dankward Struwe, Friedrich Helm, Georg Henneges, Cornelis H. M. Broeders, Mario Dalle Donne, Cornelis H. M. Broeders, Mario Dalle Donne, Walter Hame, Klaus Leinemann, Rainer Meyder, Horst Schnauder, Dieter Smidt, Helmut Jacobs, Peter Royl, Barry D. Ganapol, Charles R. Bell, Dirk Wilhelm, Leonhard Meyer, Erhard A. Fischer, Werner Maschek, Steven A. Wright, Gustav Schumacher, Peter R. Henkel, Anton Bayer, Rakesh Chawla, Walter Seifritz, Rudolf Schulten, Dieter Vollath, Horst Wedemeyer, Helmut Elbel, Elmar Günther, L. Väth, Erhard A. Fischer, Peter Klumpp, Volker Heinzel, Rolf Huber, I. Schub, Gustav Schumacher, Samuel Carmona, Shimon Yiftah, H. Küsters, Philipp Schmuck, Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher, Franklyn M. Clikeman, Sai-Chi Mo, Karl O. Ott, Gary Alan Harms, H. P. Chou, R. H. Johnson, K. Baumung, K. Böhnel, H. Bluhm)
Dr. Karl E. J. Wirtz Biographical Notes

A Helium-Cooled, Poloidal Blanket with Ceramic Breeder and Beryllium Multiplier for the Next European Torus

Mario Dalle Donne, Ulrich Fischer, Marko Küchle

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 15-28

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33707

On the Development and Application of Quantitative Methods in Nuclear Reactor Regulation

Leslie Cave, William E. Kastenberg

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 29-42

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33708

BACCHUS-3D/SP, A Computer Program to Describe Transient Three-Dimensional Single Phase Flow in LMFBR Rod Bundles

Maurizio Bottoni, Burkhardt Dorr, Christoph Homann, Dankward Struwe

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 43-67

Technical Paper / Fission Rector / dx.doi.org/10.13182/NT85-A33709

Measurements and Calculations of Reactivity Effects of Material Rearrangements in a Plutonium-Fueled Fast Reactor Rod Lattice

Friedrich Helm, Georg Henneges

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 68-81

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33710

Conceptual Design of a (Pu,U)O₂ Core with a Tight Fuel Rod Lattice for an Advanced Pressurized Light Water Reactor

Cornelis H. M. Broeders, Mario Dalle Donne

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 82-95

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33711

Neutron Physics Investigations for Advanced Pressurized Water Reactors

Cornelis H. M. Broeders

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 96-110

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33712

Critical Heat Flux Correlation for Triangular Arrays of Rod Bundles with Tight Lattices, Including the Spiral Spacer Effect

Mario Dalle Donne, Walter Hame

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 111-124

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33713

A New In-Depth Training Concept for Nuclear Power Plant Operator

Klaus Leinemann, Rainer Meyder, Horst Schnauder, Dieter Smidt

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 125-130

Technical Paper / Fission Rector / dx.doi.org/10.13182/NT85-A33714

Analytical Correlations for Rayleigh-Taylor Instability Growth

Helmut Jacobs

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 131-144

Technical Paper / Fusion / dx.doi.org/10.13182/NT85-A33715

A Study of Fuel Removal via Inner Blanket Intersubassembly Gaps During the Disruption Phase of Hypothetical Loss of Flow Accidents in Heterogeneous LMFBR Cores

Peter Royl, Barry D. Ganapol, Charles R. Bell

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 145-161

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33716

An Experimental Investigation of Fuel Expansion During Core Disruptive Accidents in Liquid-Metal Fast Breeder Reactors Using Simulant Materials

Dirk Wilhelm, Leonhard Meyer

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 162-172

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33717

The Role of Vapor Bubble Dynamics During Energetic Power Excursions in Fast Reactor Core Disruptive Accidents

Erhard A. Fischer, Werner Maschek

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 173-186

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33718

In-Pile Observations of Fuel and Clad Relocation During LMFBR Core Disruptive Accidents in the STAR Experiments

Steven A. Wright, Gustav Schumacher, Peter R. Henkel

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 187-216

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33719

Assessment of the Risk Resulting from Postulated Accidents in Nuclear Power Plants: An Interim Report on Advanced Studies

Anton Bayer

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 217-227

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33720

The Possible Role of ²³⁵U-Pu Fueled Advanced Pressurized Water Reactors

Rakesh Chawla, Walter Seifritz

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 228-235

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33721

Nuclear Energy for Coal and Steel

Rudolf Schulten

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 236-239

Technical Paper / Fuel Cycle / dx.doi.org/10.13182/NT85-A33722

On the Dissolution of (U,Pu)O₂ Solid Solutions with Different Plutonium Contents in Boiling Nitric Acid

Dieter Vollath, Horst Wedemeyer, Helmut Elbel, Elmar Günther

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 240-245

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A33723

Modeling Changes in the Fission Gas Behavior Code LAKU Based on Recent Analysis of Experiments

L. Väth, Erhard A. Fischer

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 246-257

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33724

Analysis of the Macro- and Microeconomic Aspects of Advanced Pressurized Water Reactors

Peter Klumpp

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 258-271

Technical Paper / Economic / dx.doi.org/10.13182/NT85-A33725

Delay of the Attack of Liquid Steel on Niobium by a Multilayer Coating

Volker Heinzel, Rolf Huber, I. Schub, Gustav Schumacher

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 272-288

Technical Paper / Material / dx.doi.org/10.13182/NT85-A33726

The (n,2n) and (n,3n) Reactions of Lead, A Potential Neutron Amplifier for Fusion Blankets

Samuel Carmona, Shimon Yiftah

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 289-295

Technical Paper / Material / dx.doi.org/10.13182/NT85-A33727

A Review of Improvements of Evaluated Minor Transactinium Isotope Neutron Data, Their Qualification by Integral Experiments, and Remaining Data Requirements

H. Küsters

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 296-313

Technical Paper / Radioisotopes and Isotope / dx.doi.org/10.13182/NT85-A33728

An Efficient Method to Improve Flow Representation Across Abrupt Changes of Cross-Sectional Areas

Philipp Schmuck

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 314-325

Technical Paper / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT85-A33729

In-Pile Determination of Fuel Disruption Mechanisms Under LMFBR Loss-of- Flow Accident Conditions

Steven A. Wright, Erhard A. Fischer, Peter K. Mast, Gustav Schumacher

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 326-340

Technical Paper / Analyse / dx.doi.org/10.13182/NT85-A33730

Neutron Reaction Rate Measurements as Tests of Diffusion Calculations in a Fast Breeder Blanket Facility

Franklyn M. Clikeman, Sai-Chi Mo, Karl O. Ott, Gary Alan Harms, H. P. Chou, R. H. Johnson

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 341-352

Technical Paper / Analyse / dx.doi.org/10.13182/NT85-A33731

The CABRI Fast Neutron Hodoscope

K. Baumung, K. Böhnel, H. Bluhm

Nuclear Technology / Volume 71 / Number 1 / October 1985 / Pages 353-365

Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33732

Number 2

Table of Contents
Authors(Mamdouh Shoukri, Abd-el-elah Tahir, Michael B. Carver, Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich, Yukiharu Ohga, Kohyu Fukunishi, Om Pal Singh, P. Bhaskar Rao, O. K. Tallent, J. C. Mailen, K. E. Dodson, James L. Kelly, Robert U. Mulder, Chaim J. Babad, Roderick D. MacDonald, Ian J. Hastings, Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith, Ivars Neretnieks, Craig L. Timmerman, Ken H. Oma, Alexander P. Murray, David A. Eckhardt, Sharon L. Weisberg, M. O. Menlove, J. E. Swansen, Minsun Ouyang, Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler)

Numerical Simulation of Two-Phase Flow in Horizontal Interconnected Subchannels

Mamdouh Shoukri, Abd-El-Elah Tahir, Michael B. Carver

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 375-385

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33690

Analysis of Thermal Reactor Benchmarks with Design Codes Based on ENDF/B-V Data

Mark L. Williams, R. Q. Wright, Brian A. Worley, Odelli Ozer, Walter J. Eich

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 386-401

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33691

A Reactor Water Level and Pressure Prediction Method Under Small Loss-of-Coolant-Accident Conditions in Boiling Water Reactors

Yukiharu Ohga, Kohyu Fukunishi

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 402-410

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33692

Dynamics of Fuel Vapor Pressure Buildup in Voided LMFBR Cores During the Transient Heating and Its Effect on the Energy Release in a Core Disruptive Accident

Om Pal Singh, P. Bhaskar Rao

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 411-416

Technical Paper / Nuclear Safety / dx.doi.org/10.13182/NT85-A33693

Purex Diluent Chemical Degradation

O. K. Tallent, J. C. Mailen, K. E. Dodson

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 417-425

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A33694

Experimental Investigation of the Iodine Partition Coefficient

James L. Kelly, Robert U. Mulder, Chaim J. Babad

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 426-429

Technical Paper / Chemical Processing / dx.doi.org/10.13182/NT85-A33695

Graphite Disk UO₂ Fuel Elements Designed for Extended Burnups at High Powers

Roderick D. MacDonald, Ian J. Hastings

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 430-444

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33696

Statistical Patterns of Fuel Failure in Stainless Steel Clad Light Water Reactor Fuel Rods

Gary S. Was, Ronald Christensen, Chang Park, Richard W. Smith

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 445-457

Technical Paper / Nuclear Fuel / dx.doi.org/10.13182/NT85-A33697

Diffusivities of Some Constituents in Compacted Wet Bentonite Clay and the Impact on Radionuclide Migration in the Buffer

Ivars Neretnieks

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 458-470

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33698

A Pilot-Scale Radioactive Test Using In Situ Vitrification

Craig L. Timmerman, Ken H. Oma

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 471-481

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33699

Dilute Chemical Decontamination Process for Pressurized and Boiling Water Reactor Applications

Alexander P. Murray, David A. Eckhardt, Sharon L. Weisberg

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 482-496

Technical Paper / Radioactive Waste Management / dx.doi.org/10.13182/NT85-A33700

A High-Performance Neutron Time Correlation Counter

H. O. Menlove, J. E. Swansen

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 497-505

Technical Paper / Analyses / dx.doi.org/10.13182/NT85-A33701

An Iterative Correction Method for Nondestructive Plutonium Waste Assay

Minsun Ouyang

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 506-511

Technical Paper / Analyses / dx.doi.org/10.13182/NT85-A33702

Computer Graphics to Separate Neutron from Gamma-Ray Spectra, Applied to the Measurement of Neutron Attenuation Coefficients Using an NE-213 Scintillator

Martin E. Nelson, Dean A. Miller, Peter F. Wiggins, Gordon Riel, Thomas D. Strickler

Nuclear Technology / Volume 71 / Number 2 / November 1985 / Pages 512-519

Technical Paper / Technique / dx.doi.org/10.13182/NT85-A33703

Number 3

Table of Contents
Authors(Farhang Sefidvash, Dawk Hwan Ahn, Samuel H. Levine, Takanobu Kamei, Mitsuaki Yamaoka, Yasuyuki Moriki, Masao Suzuki, Kazuo Arie, Martin Victor Polley, Shinji Tokumasu, Michihiro Ozawa, Hiroshi Hiranuma, Michiro Yokomi, Junichi Tanji, Shunsuke Utena, Bernhard Kienzler, Rainer H. Köster, Jitze Bergsma, Robert B. Helmholdt, Roel J. Heijboer, T. C. Wiencek, R. F. Domagala, H. R. Thresh, Yoshiko Harima, Kohtaro Ueki, Otohiko Aizawa, K. Tasaka, Y. Koizumi, Y. Kukita, H. Nakamura, Y. Anoda, M. Iriko, H. Kumamaru, M. Suzuki, James Y. Yaung, D. Okrent, A. R. Wazzan)
Technical Reviewers

A Fluidized-Bed Nuclear Reactor Concept

Farhang Sefidvash

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 527-534

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33675

Automatic Optimized Reload and Depletion Method for a Pressurized Water Reactor

Dawk Hwan Ahn, Samuel H. Levine

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 535-547

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33676

An Axially and Radially Two-Zoned Large Liquid-Metal Fast Breeder Reactor Core Concept

Takanobu Kamei, Mitsuaki Yamaoka, Yasuyuki Moriki, Masao Suzuki, Kazuo Arie

Nuclear Technology / Volume 71 / Number 3 / December 1985 / Pages 548-556

Technical Paper / Fission Reactor / dx.doi.org/10.13182/NT85-A33677