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ORNL-1154.txt
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ORNL-1154
This document consists of 225 pages.
Copy §i of 203 . Series A
Contract No. W-7405, Eng-26
AIRCRAFT NUCLEAR PROPULSION PROJECT
QUARTERLY PROGRESS REPORT
for Period Ending September 10, 1951
R. C. Briant
Director, ANP Project
C. B. Ellas
Coordinator, ANP Project
Edited by:
W. B, Cottrell
DATE 1SSUED:
OAK RIDGE NATIONAL LABORATORY
Operated by
CARBIDE AND CARBON CHEMICALS COMPANY
A Division of Union Carbide and Carbon Corporation
Post Dffice Box P
0ak Ridge, Tennessee
ORNL-1154
Progress Report
INTERNAL DISTRIBUTION
1 G. T. Felbeck (C&CCC) 37 R. W. Stoughton
2-3 Chemistry Library 38 F. R. Bruce
4 Physics Library 39 H. W. Savage
5 Biology Library 40 W. K. Eister
6 Health Physics Library 41 A. S. Householder
7 Metallurgy Library 42 C. B. Graham
8-9 Training School Library 43 R. N. Lyon
10-13 Central Files 44 C. P. Keim
14 C. E. Center 45 W. R. Gall
15 C. E. lLarson 46 A. J. Miller
16 W. B. Humes (K-25) 47 R. W. Schroeder
17 W. D. Lavers (Y-12) 48 D. S. Billington
18 A. M. Weinberg 49 E. P. Blizard
19 E. H. Taylor 50 C. E. Clifford
20 E. D. Shipley 51 G. H. Clewett
21 £. J. Murphy 52 A. D. Callihanr
22 F. C. VonderLlage 53 R. S. Livingston
23 R. C. Briant 54 W. D. Manly
24 J. A, Swartout 55 J. L. Meem
25 C. B. Ellis 56 C. D. Susano
26 A. H. Snell 57 W. B. Cottrell
27 A. Hollaender 58 W. M. Breazeale
28 F. L. Steahly 59 W. R. Grimes
29 K. Z. Morgan 60 A. Brasunas
30 D, W. Cardwell 61 N. M. Smaith
31 M. T. Kelley 62 H. F. Poppendiek
32 E. M. King 63 F. C. Uffelman
33 C. E. Winters 64 D. D. Cowen
34 J. A. Lane 65 P. M. Reyling
35 J. H. Buck 66-75 ANP Library
36 J. P. G111l 76-81 Central Files (0.P.)
82-103
104-113
114
115-122
123
124-126
127
128
129-134
135
136
137-141
142-145
146
147
148-151
152
153-156
157-159
160
161-162
163-166
167
168-169
170-171
172
173
174-175
176-179
180-188
189-203
ORNL-1154
- Progress Report
EXTERNAL DISTRIBUTION
Aircraft Nuclear Propulsion Project, 0Oak Ridge
Argonne National Laboratory
Armed Forces Special Weapons Project (Sandia)
Atomic Energy Commission, Washington
Battelle Memorial Institute
Brookhaven National Laboratory
Bureau of Aeronautics
Bureau of Ships
Carbide and Carbon Chemicals Company (Y-12)
Chicago Patent Group
Chief of Naval Research
duPont Company
General Electric Company, Richland
H. K. Ferguson Company
Hanford Operations Office
Idaho Operations Office
Towa State College
Knolls Atomic Power Laboratory
Los Alamos
Massachusetts Institute of Technology (Kaufmann)
Mound Laboratory
National Advisory Committee for Aeronautics, Cleveland
National Advisory Committee for Aeronautics, Washington
New York Operations Office
North American Aviation, Inc.
Patent Branch, Washington
Savannah River Operations Office
University of California Radiation Laboratory
Westinghouse Electric Corporation
Wright Air Development Center
Technical Information Service, Oak Ridge
data as
of 1946.
111
iv
Reports previously issued in this series are as follows:
ORNL-528 Period Ending November 30, 1949
ORNL-629 Period Ending February 28, 1950
ORNL-768 Period Ending May 31, 1950
ORNL-858 Period Ending August 31, 1950
ORNL-919 Period Ending December 10, 1950
ANP-60 Period Ending March 10, 1951
ANP-65 Period Ending June 10, 1951
Ll
TABLE OF CONTENTS
SUMMARY _
Part 1. REACTOR THEORY AND DESIGN
1. THE AIRCRAFT RFACTOR EXPERIMENT .
Core Design |
Fluid Circuit
Heat-disposal circuit :
Contamination of helium system
Control of the ARE
Liquid-fuel control system
Solid absorber rod design
Electronic computor design
Electrical Circuit
Remo te-Handling Equipment
Building Facility for the ARE
2. EXPERIMENTAL REACTOR ENGINEERING
Liquid-Fuel Systems
Pump Development
Centrifugal pumps for figure-eight loops
~ARE pump design
Canned-rotor pump
Level tank pump
Electromagnetic pumps
Test Loops
Calibration loop
Sodium manometer loop
Seal Tests
Frozen-sodium seal
Bellows seal
Graphitar and tool steel seal
Instrumentation
Stress-Rupture Tests
Self-Welding Tests
Valve-Packing Experiments
17
PAGE
~NO.
10
10
10
11
11
11
12
12
12
12
i4
14
15
15
16
17
17
20
20
20
20
21
21
21
23
23
24
24
Contamination of Liquid-Metal Systems
Cleaning of liquid-metal systems
Purification of liquid metals
Purification of inert gases
Analytical results with sodium
Investigation of Sodium Condensation
ARE Component Tests
Heat-Exchanger Tests
Building Modifications and Experimental Facilities
Alkali Metals Manual
3. REACTOR PHYSICS
IBM Calculations
Production report
The multiregion reactor problem
Cylindrical multigroup calculation
The effect of the borom blanket in the ANP reactor
Statics of the Aircrafc Reactor Experiment
Summary of calculations on the ARE
Estimated critical mass of the ARE
Control rod effectiveness
Kinetics of the Aircraft Reactor Experiment
Mass-reactivity coefficient
Fuel conductivity
Neutron lifetime
Start-up accident
Coolant temperature
Preparatory Physics Calculations
Correction to "Wigner formula for resonance escape" probability
Effect of "Wigner formula for resonance escape’™ correction
The transmission coefficient of the B,C curtain in the ANP
and ABE reactors
Heating in the boron carbide curtazin in the AMP reactor
Temperature savings in the ANP reactor
The Sodium Hydroxide Reactor
4. CRITICAL EXPERIMENTS
Critical Assembly of Air-Water Reactor
PAGE
ND.
25
25
26
26
26
27
27
28
28
30
31
32
32
33
33
33
34
34
36
37
48
49
49
56
36
60
60
64
66
66
67
70
19
79
Critical Assemblvy of Graphite Reacter
Part II. SHIELDING RESEARCH
BULK SHIELDING REACTOR
Reactor Operation
Mock-Up of the Unit Shield
Mock-Up of the Divided Shield
LID TANK
DUCT TEST
SHIELDING CALCULATIONS
Analysis of Bulk Shielding Reactor Neutron Data
Interpretation of Lid Tank Gafima-flay Data
Shielding Calculations for the ARE
Activation of nitrogen and helium in the ARE reactor pit
Activation of impurities in BeO :
Detection of leaks in the fuel elements by means of radiocactive
tracers ‘
NDA Divided-Shield Studies
Use of NH, as a Shielding Material
Mechanical requirements of an ammonia shield
Calculational procedure &
Comparison of shield weights using NH; and H O
NUCLEAR MEASUREMENTS
The 5-Mev Van de Graaff Accelerator
Measurement of the (n,2n) Reaction in Beryilium
Bremsstrahlung from Li8
Radiation detection equipment
Bremsstrahlung activity
Time~of-Flight Néutron Spectrdmeter
. PAGE
NO.
80
83
B3
83
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87
89
91
91
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92
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93
93
93
94
95
95
96
97
97
97
98
98
98
100
S vil
Part III. MATERIALS RESEARCH
10. CORROSICN RESEARCH
Static Corrosion by Fluoride Fuels
The pretreatment process
Corrosion of structural metals
Corrosion of platinum
Static Corrosion by Moderator Coolants
Capsule technique with hydroxides
Corrosion by sodium hydroxide
Corrosion by potassium hydroxide
Corrosion by other hydroxides
Corrosion by binary hydrogenous systems
Static Corrosion by Fluoride Coolant Mixtures
Static Corrosion by Sodium
Static Corrosion Test of a Reactor System
Mass Transfer Phenomenon in Static Corrosion
Chemical-reaction mechanism for mass traansfer
Experimental evidence
Dynamic Corrosion Tests in Thermal-Convection Loops
Corrosion by lithium and lead
Corrosion by seodium
Dynamic Corrosion Tests in Forced-Convection Loops
11. PHYSICAL PROPERTIES AND HEAT-TRANSFER RESEARCH
Investigation of Free Convection Within Liquid-Fuel Elements
Theoretical analysis of natural convection
Measurement of the fuel-element temperature distribution
Measurement of the fuel-element velocity distribution
Physical Properties
Heat capacity
Thermal conductivity of liquids
Thermal conductivity of solids
Falling-ball viscometer
Brookfield viscometer
Vapor pressure
Density
Heat-Transfer Coefficients
vili
PAGE
NO.
103
104
104
106
110
112
113
113
113
118
118
118
118
122
122
122
123
124
124
129
131
132
132
132
133
134
134
134
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135
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136
136
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137
12.
13.
Heat transfer in fused hydroxides and salts
Heat transfer in boiling-liquid-metal systems
Heat transfer in molten lithium
METALLURGY AND CERAMICS
Welding of Inconel
Tensile tests
Fatigue tests
All-weld-metal tensile tests
Corrosion of welds
Special weld tests
Welding of Molybdenum
Creep of Metals in Controlled Atmospheres
Creep of 316 stainless steel
Creep of inconel :
Creep of niobium
Creep test of loaded inconel tube
Stress-Relaxation Tests
Fuel-Element Fabrication
Hot rolling
Mechanically formed matrix
Loose-powder sintering
Rubberstatic pressing
Compatibility of potential fuel-element materials
Control-Rod Fabrication
Metal Cladding of Beryllium Oxide
Refractory Metals
Ceramics Laboratory
CHEMISTRY OF HIGH-TEMPERATURE LIQUIDS
Fuel Development
Low-melting fluoride systems
Preparation of UF,
Homogeneous fuels
Moderator~Coolant Development
Preparation of pure sodium hydroxide
Preparation of other hydroxides
PAGE
137
138
139
141
141
141
143
144
145
145
145
145
146
146
146
146
147
147
147
149
149
149
151
151
152
152
152
154
154
155
159
161
162
162
165
1X
Decomposition pressures of hydroxides
Binary hydroxide systems
Hydroxide-fluoride systenms
Hydroxide-borate systems
Coolant Development
14. RADIATION DAMAGE
Creep Under Irradiation
Radiation Effects on Thermal Conductivity
Irradiation of Fluoride Fuels
Pile irradiation of fuel capsules
Cyclotron irradiation of fuel capsules
Corrosion of Iron by Lithium Under Cyclotron Irradiation
Liquid Metals In-Pile Loop
Part IV. ALTERNATE SYSTEMS
15. SUPERCRITICAL WATER REACTOR
Outline of a Specific Design
Fuel Elements and Assemblies
Reactivity
Stabilaty
Pressure Shell
Shield
16. CIRCULATING-MODERATOR-COOLANT REACTOR: HKF
Operational Characteristics
Reactor Characteristics
Core Design
Reactor Physics
17. CIRCULATING-MODERATOR-COOLANT REACTOR: ORNL
Fluid-Circuit Specifications
PAGE
NO.
165
166
167
168
168
170
170
171
173
173
173
174
174
179
179
180
180
182
183
183
185
185
186
186
187
188
188
Fuel-Element Design
Reactor Design
18. HIGH-TEMPERATURE POWER PLANT STUDIES
Sodium-Liquid-Vepor Cmmprassorljet
Helium-Cooled Reacters
Part V. APPENDIXES
19, ANALYTICAL CHEMISTRY
Analysis of Reactor Fuels
Spectrographic results
Development of colorimetric metheds
Determination of platinum
Oxygen in Sodium
Oxygen in Lead
Oxygen in Helium .
Oxygen and Nitrogen in Lithium
Carbon in Lithium
Uranium Trifluoride in Uranium Tetrafluoride
Identification of Residue 1in Lithium-Metal Coolant System
Analytical Services
20. LIST OF BEPORTS ISSUED
‘PAGE
NO.
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188
192
1923
194
199
200
200
200
201
201
201
201
1202
202
202
203
- 204
205
X1
3.4
3'5
8.1
10.1
10.2
10.3
10.4
12.1
12.2
12.3
13.1
13.2
13.3
13.4
13.5
13.6
13.7
x11
LIST OF TABLES
TITLE
Composition and Design Data of Core 93
Volume Fractions of the Materials in the Side and Bottom
Reflectors
Summary of Calculations on the ARE Core Having 25 1b of
Uranium and Reflector 520
Calculation of Uranium Requirement for the ARE Design of
10 June 1951
B4C Transmission Coefficients
Comparison of Shield Weights Using NH; and H,0
Summary of Fluoride-Corrosion Data Obtained in 100 hr at
1000°C (1830°F)
Summary of Corrosion Data Obtained in 100-hr Tests at 815°C with
PAGE
NO.
36