The customary approach to reactor development assumes that a reactor is primarily a mechanical engineering device—that the ultimate goal of economically competitive nuclear power will be achieved by simplifying the mechanical design and by making the fuel elements more reliable. The other, basically different, view of reactor technology holds that reactors are chemical plants—that the methods which have proved so useful in rationalizing the chemical industry, i.e., the continuous handling of materials in liquid form; should lead to ultimate economies in reactor plants. This "chemical" approach to reactors has been pursued vigorously in the United States for almost a decade; it is summarized in this volume on fluid fuel reactors.
The basic simplicity of the liquid reactor—the original idea of "a pot, pump, and pipe"—has hardly persisted throughout the years. Those who have actually built and operated high-temperature, high-powered liquid reactors have become impressed with their difficulty—the difficulty primarily of handling vast amounts of radioactivity in labile form. It seems now that liquid reactor systems, when reduced to practice, are in many ways more complicated than their solid competitors; at least their complications (being in the plumbing system) are much more obtrusive than the complications of a solid fuel reactor, which lie out of sight in the core.
Yet in spite of their difficulties, the two underlying motivations for liquid and other fluid systems remain: their fuel cycle is simpler and their neutron economy is better than for solid-fueled reactors. Thus there continues to be strong incentive to develop these systems. It is the belief of fluid fuel enthusiasts that in the very long run the simplification in fuel cycle and, more important, the better neutron economy made possible by the use of fluid fuels will outweigh the difficult handling problems and ultimately weight the balance of reactor development toward these systems.
The present volume contains a summary of the work done in the United States on fluid fuel reactors. The first part deals with the aqueous homogeneous reactor; most of this work has been done at the Oak Ridge National Laboratory, with some phases of the work (on slurries) at Westinghouse Atomic Power Division and some work on phosphate solutions at Los Alamos Scientific Laboratory. The second part deals with the fused salt system, which has been investigated primarily at the Oak Ridge Laboratory; the third part deals with the bismuth-uranium system, investigated at Brookhaven National Laboratory.
It is my hope that the results described here will be helpful to all who are interested in fluid fuel systems, and that, by disseminating this information, new ideas and new approaches will be generated to help solve the remaining problems of fluid fuel reactors.
Oak Ridge, Tenn. June 1958
A.M. Weinberg, Director
Oak Ridge National Laboratory

Printed in the United States of America
Library of Congress Catalog Card No. 58-12600
First Printing, September 1958 (hardcopy)
Digital Editions Commence, January 2019 (v20181227c)
In their work on this book the editors and authors were assisted by representatives of the U.S. Atomic Energy Commission's Industrial Information Branch, Technical Information Service. Charles D. McKereghan was book project officer, and DeWitt O. Myatt guided the styling of the art. The Technical Information Service Extension at Oak Ridge put the references in final form.
The references cite a number of publications issued by the Atomic Energy Commission. These are available for inspection at the Commission's depository libraries in the United States and abroad and are sold by the Office of Technical Services, U. S. Department of Commerce, Washington 25, D. C.
The data selected, its evaluation, and the conclusions reached in this book are wholly the work of the authors, contributors, and editors.
June 1958
James A. Lane,
H. G. MacPherson,
Frank Maslan
Fluid Fuel Reactors - Part I
AQUEOUS HOMOGENEOUS REACTORS
CHAPTER 1
HOMOGENEOUS REACTORS AND THEM DEVELOPMENT
1-2. General Characteristics of Homogenous Reactors
1-6. Miscellaneous Homogeneous Types
CHAPTER 2
NUCLEAR CHARACTERISTICS OF ONE- AND TWO-REGION HOMOGENEOUS REACTORS
2-2. Nuclear Constants Used In Criticality Calculations
2-3. Fuel Concentrations and Breeding Ratios Under Initial and Steady-State Conditions
2-4. Unsteady-State Fuel Concentrations And Breeding Ratios
2-5. Safety And Stability Of Homogeneous Reactors Following Reactivity Additions
CHAPTER 3
ROPERTIES OF AQUEOUS FUEL SOLUTIONS
3-2. Solubility Relationships of Fissile and Fertile Materials
CHAPTER 4
TECHNOLOGY OF AQUEOUS SUSPENSIONS
4-1. Suspensions And Their Applications In Reactors
4-3. Preparation And Characterization Of Thorium Oxide And Its Aqueous Suspensions
4-5. Operating Experience with the Hre-2 Slurry Blanket Test Facility
4-6. Radiation Stability of Thorium Oxide Slurries
4-7. Catalytic Recombination of Radio Lytic Gases In Aqueous Thorium Oxide Slurries
CHAPTER 5
INTEGRITY OF METALS IN HOMOGENEOUS REACTOR MEDIA
5-2. Experimental Equipment for Determining Corrosion Rates
5-4. Corrosion of Type-347 Stainless Steel in Uranyl Sulfate Solutions
5 5. Radiation-Induced Corrosion of Zircaloy-2 and Zirconium
5-6. Corrosion Behavior of Titanium and Titanium Alloys in Uranyl Sulfate Solutions
5-8. Homogeneous Reactor Metallurgy
5-9. Stress-Corrosion Cracking
6-2. Core Processing: Solids Removal
6-3. Fission Product Gas Disposal
6-4. Core Processing: Solubles
6-6. Uranyl Sulfate Blanket Processing
6-7. Thorium Oxide Blanket Processing
CHAPTER 7
DESIGN AND CONSTRUCTION OF EXPERIMENTAL HOMOGENEOUS REACTORS
7-3. The Homogeneous Reactor Experiment (HRE-1) [10-13]
7-4. The Homogeneous Reactor Test (Hre-2)
7-5. The Los Alamos Power Reactor Experiments (Lapre 1 And 2)
CHAPTER 8
COMPONENT DEVELOPMENT
8-2. Primary-System Components
8-3. Supporting-System Components
CHAPTER 9
LARGE-SCALE HOMOGENEOUS REACTOR STUDIES
9-2. General Plant Layout and Design
9-3. ONE-REGION U235 BURNER REACTORS
9-4. One-Region Breeders and Converters
CHAPTER 10
HOMOGENEOUS REACTOR COST STUDIES
10-1.1 Relation between cost studies and reactor design factors.
10-1.2 Parametric cost studies at ORNL.
10-2. Bases for Cost Calculations
10-2.2 Investment, operating, and maintenance costs.
10-3. Effect Of Design Variables On The Fuel Costs In ThO2-UO3-D2O SYSTEMS [8-10]
10-4. Effect Of Design Variables on Fuel Costs in Uranium-Plutonium Systems
10-5. Fuel Costs in Dual-Purpose Plutonium Power Reactors
10-6. Fuel Costs in U235 Burner Reactors
10-7. Summary of Homogeneous Reactor Fuel-Cost Calculations
10-8. Capital Costs for Large-Scale Plants
10-9. Operating and Maintenance Costs in
Large-Scale Plants
10-10. Summary Of Estimated Power Costs
Fluid Fuel Reactors - Part II
MOLTEN-SALT REACTORS
CHAPTER 11
INTRODUCTION TO MOLTEN SALT REACTORS
CHAPTER 12
CHEMICAL ASPECTS OF MOLTEN-FLUORIDE-SALT REACTOR FUELS
12-1. Choice Of Base Or Solvent Salts
12-2. Fuel And Blanket Solutions
12-3. Physical And Thermal Properties Of Fluoride Mixtures
12-4. Production And Purification Of Fluoride Mixtures
12-5. Radiation Stability Of Fluoride Mixtures
12-6. Behavior Of Fission Products
CHAPTER 13
CONSTRUCTION MATERIALS FOR MOLTEN-SALT REACTORS
13-1. Survey Of Suitable Materials
13-2. Corrosion Of Nickel-Base Alloys By Molten Salts
13-4. Mechanical And Thermal Properties Of INOR-8
13-6. Fabrication Of A Duplex Tubing Heat Exchanger
13-8. Compatibility Of Graphite With Molten Salts And Nickel-Base Alloys
13-9. Materials For Valve Seats And Bearing Surfaces
13-10. Summary Of Material Problems
CHAPTER 14
NUCLEAR ASPECTS OF MOLTEN-SALT REACTORS
14-1. Homogeneous Reactors Fueled With U235
14-2. Homogeneous Reactors Fueled With U233
14-3. Homogeneous Reactors Fueled with Plutonium
14-4. Heterogeneous Graphite-Moderated Reactors
CHAPTER 15
EQUIPMENT FOR MOLTEN-SALT REACTOR HEAT-TRANSFER SYSTEMS
15-2. Heat Exchangers, Expansion Tanks, And Drain Tanks
CHAPTER 16
AIRCRAFT REACTOR EXPERIMENT
CHAPTER 17
CONCEPTUAL DESIGN OF A POWER REACTOR
17-1. Fuel And Blanket Systems
17-2. Heat-Transfer Circuits And Turbine Generator
17-3. Remote Maintenance Provisions
17-4. Molten-Salt Transfer Equipment
17-6. Chemical Reprocessing Method
Fluid Fuel Reactors -
Part III
LIQUID-METAL FUEL REACTORS
CHAPTER 18
INTRODUCTION TO LIQUID-METAL FUEL REACTORS
18-2. General Characteristics Of Liquid Metal Fuel Reactors
18-3. Liquid Metal Fuel Reactor Types
CHAPTER 19
REACTOR PHYSICS FOR LIQUID METAL REACTOR DESIGN
CHAPTER 20
COMPOSITION AND PROPERTIES OF
LIQUID-METAL FUELS
20-3. Physical Properties Of Solutions
20-6. Thorium Bismuthide Blanket Slurry
20-6.5 Engineering studies of slurries.
20-7. Thorium Compound Slurries
CHAPTER 21
MATERIALS OF CONSTRUCTION-METALLURGY
22-2. Volatile Fission Product Removal [20]
22-3. Fused Chloride Salt Process
22-4. Fluoride Volatility Process For Fission Products
22-5. Noble Fission Product Removal
22-6. Blanket Chemical Processing
22-7. Economics Of Chemical Processing
CHAPTER 24
LIQUID METAL FUEL REACTOR DESIGN STUDY
24-1.Comparison Of Two-Fluid And Single-Fluid
LMFR Designs
24-2. Two-Fluid Reactor Design
24-4. Single-Fluid Reactor Design
CHAPTER 25
ADDITIONAL LIQUID METAL REACTORS
25-1. Liquid Metal Fuel Gas-Cooled Reactor