ORNL-2095: 1956-05 (18.9 MB PDF)

198 Pages·2002·18.47 MB·English

This document c0nsists of 198 pages.
~opJ?#of 300 eopies. Series A.
AiRCRAFT REACTOR ENGINEERING DlVlSlON
A. P. Froas sad A. W. Savslaineri
May 19%
DATE ISSUED
OAK RIDGE NATIONAL LABORATORY
Operated by
UNlQN CARBSDE NUCLEAR COMPANY
A Division of Union Carbide and Carbon Corporation
Post Office BOX X
Oak Ridge, Tennessee
This document contains Reai'rkted Dote as defined in the Atomie
Energy Aet of 1954. Its transmittal or the disclosure of its contents
in any rnenner PO an unoufharized pet5on is prohibited.
lMTERNAL DISTRISUTIQN
1. A. A. AbcsttieElo 47. W. K. Ergen
2. R. 6. Affel 48. 8. E. Ferguson
3. J. C. Amos 49. J. Foster
4. B. B. Bechulis 50. A. P. Fraas
5. C. J. Barton 51. J. H. Frye
6. 5. E. Beofle 52. W. T. Furgerson
7. M. Bender 53. B. L. Gray
8. H. W. Bertini 54. R. J. Gray
9. D. s. BiIlington 55. €3. %. Greenstreet
w.
10. F. F. Blankenship 56. R. Grimes
11. E. P. BBizard 57. A. G. Grindell
12. A. L. Bock 58. 8. L. Heestond
w.
13. C. J. Borkowski 59. Heltsn
14. w. F. Bsudreeu E. E. Hoffman
15. 6. E. Boyd 61. H. w. Hoffman
16. M. A. Bredig 62. A. Hollcsender
17. E. b. Breeding 63. L. B. Holland
18. R. 8. Briggs $4. A. s. Householder
19. W. E. Browning 65. 4. T. Howe
26. F. w. Bruce 64. T. L. Hudssfl
21. A. D. Callihan 47. W. H. Jordan
22. B. W. Cardwell 48. G.W . Keilholtz
23. W. S. Carlsmith 69. C. P. Keim
24. L. P. Carpenter 70. I=. t. Melfer
25. C. E. Center (K-25) 71. M. T. Kelley
26. R. A. Charpie 72. F. Kertesz
27. R. B. Clarke 73. b. J. Keyes
28. c. E. Clifford 74. E. M. King
29. W. G. Cob$ 75. M. E. Lackey
30. 9. A. Gonlin 74. J. A. Cane
31. d. H. Coobs sa. E. M. Lees
2.W . B. Cottrell 78. R. B. Lindauer
33. D. B. Cowen 79. W. S. Livingston
34. G. A. Cristy $8. R. N. Lyon
35. S. J. Cromer $1. F. c. Maienschein
36. w. s. Crouse 82. W. B. Manly
37. F. L. Culler 83. E. W. Mann
38. c. w, Cvnningharn 84. L. A. Mann
39. R. Curry $5. w. B. McDonald
40. S. M. Decamp $6. W. E. MsPherson
41. J. H, BeVan $7. F. W. McQuilkin
42. t. M. Boney $8. W. V. Meghreblion
43. D. A. Douglas 89. R. P. Mitfod
44. E. R. Bytko 98. A. J. Miller
45. W. K. Eister 91. R. E. Moore
46. b. B. Ernlef (K-25) 92. d. 6. Morgan
...
83. K. Z. Morgan 123.- A. L. Southern
94. J. P. Murray (Y-12) 124. W. J. Stelzman
95. M. L. Nelson 125. E. Storto
96. G, J. Nessle 126. c. DeS usan0
97. R. F. Newton $29. J. A. Swartout
98. 8. B. Oliver 128. A. Taboada
99. w. R. Osborn 129. E. H. TayloP
IQO L. G. 0verholser laoR. . E. Thoma
0
101. P. patsiarea 131. D. B. Ytauger
182. R. W. Peelfe 132. E. R. Van Artsdalen
103. A. M. Perry 133. E. V'i ncens
e.
164. J. Pigg 134. C. S. Walker
105. H. F. Poppendisk 13%. D. 8. Ward
106. P. M. Reyliq 136. G. M. Watson
109. A. E. Rich 837, A. M. Weinberg
108. M. P. Robinson 138. J. C. White
109. 6. Samuel5 139. 6. D. Whitman
'I 18. H. w. Savage '148. E. P. Wigner (csnsultant)
111. A. W. Sawlainen 141. G. 6. Williams
112. R. B. Schultheiss 842. J. c. Wilson
113. w. b. Scott 143. c. E. WinteFS
114. E. 8. Shipley 844. M e M. YaFQSk
115. A. Simon 145. J. Zasler
116. 8. Sismen 146. c. D. Zerby
197. d. Sites 147-156. 698NL - Y-12 Technical Library
118. M. J. Skinner Document Reference Section
119. G. M. Slaughter 157-189. Laboratory Records Department
128. 6. P. Smith 190. Laboratory Records, QRNL R. C.
'125. P. G. Smith '191-193. Central Research Library
122. A. H. Sneil
'194. AF Plant Representative, Baltimore
195. AF Piant Rep~esentative,B urbonk
196, AF Plant Representative, Marietta
197-199. AF Plant Representative, Santa Monica
200-261. AF Plant Representative, Seattle
202. kF Plant Representative, Wood-Ridge
203. Air Research and Development Command (RDGN)
384. Air Technical lntelligence Center
205 Air University Library
206. Allison Division
207-209. ANP Project Office, Fort Worth
280. Argonne National Laboratory
211. Armed Forces Special Weapons Project, Sandia
212. Armed Forces Special Weapons Project, Washington
213. Assistant Secretary of the Air Force, R&D
214-219. Atomic Energy Commission, Washington
220. Bureau of Aeronautics
...
ILI
221. Bureau of Aeronautics General Representative
222. Chieago Operations Office
223. Chicago Patent Group
224. Chief of Naval Research
225. Convoir-General Dynamics Corporation
226-229. General Electric Company (ANPD)
238 Hartford Area Office
D
231. Headquarters, Air Foree Special Weapons Center
232. Idaho Operotions Office
233. Lockland Area Office
234. Los Alarnos Scientific Laboratory
235. National Advisory Committee for Aeronautics, Cleveland
236. National Advisory Committee for Aeronautics, Washington
23%. Naval Air Development and Material Center
238. Navel Research Laboratory
239. North American Aviation, lnc. (Aerophysics Division)
240 Nuclear Development Corporation of Ameriea
a
241 * Office of the Chief of Naval Operations @$-361)
242. Patent Branch, Washington
243-267. Pmtt & Whitney Aircraft Division (Fox Project)
268. Sandie Corporation
269. School of Aviation Medicine
270. USAF Project RAND
271. University of &a1 ifornia Radiation Laboratory, Livermore
272-289. Wright Air Development Center (WC6SB-3)
288 - 298 e Te_c_h nic.a l Information Service Extension, oak Ridge
30. Division of Research and Bevelopment, AEC, OR0
,w.. .. .. ,... > jr
iv
...w ’
.... /
FOREWORD
The Aircraft Reactor Test (ART) program was launched early in 1954. The reasoning
and experiments that led first to the choice of the circulatlngl-dluo~ide-fraelr eactor concept
and then to the reflector-moderated reactor configuration have been presented in previous
documents. These inciude e presentation by W. C. Baiant to the USAF Advisory Csm-
snittee, outlining the objective and status of the ORNL-ANP Progmm (QRNL report
CF-53-2-126),s ummaries of the preliminary design work on the Aircraft Reactor Experi-
ment (ARE) (ORB\(b-1234) and the operation of the ARE (ORNb-lW)# and a compre-
hensive summery of OWNL-ANP aircraft power plant designs up to May 1954 (ORNL-172pD.
The preliminary layout of the ART and facility was given in the ART hazards repd
fORNL-8875) and in the ANP Project Quarterly Progress Report for the Period Endmg
December 10, 1354 (oBs\I!--1816).
The information compiled in this design report is intended to present a fairly detailed
picture of the ART design as of its approaching completion. It is expected that the
design CIS defined in this report wilS be changed somewhat as information is derived
from component test experience, further analytical work, or fabricationat problems.
ACKNOWLEDGMENTS
Most of the material presented here has appeared previously in quarterly progress
reportsl special ARE and ART reports, or ART design memorandums and date sheets.
The work of all members of the ANP staff is therefore represented here, and their contri-
butions are thus acknowledged.
V

EGRET
PART I
DESIGN CRlTERlA .......................................................... 3
Mi B itory Requirements ..................................................... ..' ...... _..... ....... ...... ............... 3
~ ~ ~
Weaetor Design Criteria .............................. ...................................................... 3
The Circulating-Fuel Reflector-Moderated Reactor ........~..........I.. ...... ........................... 4
~
PART BI
THE ART ASSEMBLY ........ ....................................................................................... 9
The Reactor Assembly ................... ..... .......................... 9
~ ~
Reactor Dimensions ................................................................................... ............................... 9
Ref1e Ctor-MQderatQI' ....... ..... ..... . .... .. ....... . .. .. ... ... .... ...... .. .... .... .... ~.. ... ....... ~...... ~ ... ... ...... ... .... ..... ... .. .. .... ..... ....~ .._ 25
~
Fuel system ........... ~....... ................................... ............ .. . . . . . . 25
~
Core Hydrodynami cs .......... ......... .......................... .......... ...~... ................... ................... ...................... ..... 25
~ ~ ~ I ~
Pumps and Expansion Tank ...... .........'....... ........ ................................... 29
~ ~ ~
Fi 11-and-Drain System (Including Enricher) ................................................................ 32
Sampling System ..... ................................ ............L......... .......................................... ............ ................... 35
~ ~ ~ ~ ~ ~
Fuel Recovery System ........... .............................. ... ............................. 35
~
Heat Exchanger and Heat Dumps ............... ................................................ ..... ........... ,........... ....._,..... 35
~ ~ ~
Off-Gas System ..................................................... ......... .................................. 38
Aircraft-Type Shield ........................ ....~.. ... ................. ..f. ........ ......... ......................I ......... ............ ......... .... 36
~ ~ ~ ~ ~
Controls and Instrumentation ............................................................. '~. 46
Auxi lisry Systems ............ '.. ............... ......... ...... ................................ 41
~ ~ ~
....................... ..................... . ................ .......................................... ......... ....~... ......... 41
~ ~ '
.........i............~............i........ 4%
.. .. . . . 42
Fuel and Sodium Pump Lubricating and Cooling Oil Systems .............................................................. 42
Process Water System ....................................... 42
The Facility ................... ...................... ................... ...................... ...................... 43
~ ~ ~
The Building .......... ....................................................... 43
The React~rA ssem 43
The Shielding Expe 47
PART Ill
DESIGN AND DEVELOPMENT STUD1 ES 51
Fuel Development ................................................................................................................. .......... ............~ . 51
~
Structural Material ................. .............................................. 52
Corrosion of Structural Materials ........... ...... ......... .... ......... ....~... ......................... 52
~ ~
Radiation Effects on Strueturai Materials ......................................................... ...... _.....~... ... ......... ........... 55
~ ~
StrueturaJ Design Analyses .......................................................................................................................... 56
The Reactor ............................................ ................................ ........................................................... 56
Auxi I iary Components .......... ............... . .. . . . .. 61
~
vi i
Radiation Heating on the ART Equatorial Plene in the Vicinity of the
Fuel-to-NaK Heat Exchanger ...................................................................................................................... 64
Radiation Heating in Various Regions of the North Head ........................................................................ 67
Beto- and Gamma-Ray Activity in the Fuel-Expansion Chamber and the Off-Gss System .................. 6%
PART IV
ENG/NEERING TEST UNIT ............................................................................. ................ ....... 75
Specific Test Qbiectives ....................... ....... .......................................................... 75
Warmup and Shakedown Testing ............................................................................................. 76
Operating Tests ............................................................. 76
Reactor Assembly .... ..... ......... ................................................................................... 76
Reactor Disassembly ...................................................................................................................................... 8%
PART V
CONSTRUCTION AND OPERATIBN .............................................................. 85
Plans for In~taIlati~ofn the ART ....... .................................................................................... 85
Operation of the ART ................................................. 85
Filling and Heating .................................................................................................................................... 85
Enriching to Critical .. 86
bow-Power-level Experiments ....... 87
QperCItioR st Power ............. .................................................................................................................. $8
Plans fer Disassembly ....................... 88
PART VI
STATUP OF DESIGN AND DEVELOPMENT ................................................................................................ 99
APPENDIX A
FLOW DIAGRAMS .............................................................................................................................................. 107
APPENDIX 5
PHOTOGRAPHS OF REACTOR MODELS AND STAGES IN THE CONSTRUCTION QF THE
ART FAClLlTj’ .............................................................................................................................................. 137
BIBLIOGRAPHY ................................................................................................................................................ 173
...
VIII
...=... ..... . > . $
Figure Me. Page
1 Vertical Section Through Reactor Assembly 10
2 Horizontal Section Through Fuel Pump-Expansion Tank Region 16
3 Horizontal Section Through Sodium Pumps 17
4 Vertical Section Through Lead-Water Shield 18
5 Effect of Reactor Dimensions on Concentration sf U235i n ~ues 19
6 Effect of Reactor Dimensions and External FU~VIo lume on bote1 L J ’ ~ ~ 20
t n ves tmen t
7 Effect 5%R eactor Dimensions on Outside Peak-to-Average Power-Density 21
RatiQ in Core of Reflector-Moderated Reactor
8 Effect of Reactor Dimensions on Percentage of Fissions Caused by 21
Thermal Neutrons
9 Partioily Assembled Island Showing the tower Half of the lnconel Core 28
Shell and the Upper kdf of the Beryllium Reflector for the Htgh-
Temperature Critical Assembly
Outer Core Shell and Partially Assembled Beryllium Reflector of the 23
High-Temperature Critical Assembly
11 CompEeted High-Temperature Critical Assembly of the Reflecror-Moder- 24
ate$ Circulating-Fuel Reactor
12 COR? LQyQUt 27
13 Diagram of Core Flow System Showing Relations Between the Inlet 29
Headers, Inlet Guide Vanes, and Core
14 Section Through Fuel Pump-Expansion Tank Region Showing Xenon- 33
Removal System of the Fuel Pump
15 Schematic Diagram of Fuel Fill-and-Drain System, Including Enriches 34
16 Fuel Fill-and-Drain Tank Cooling System 35
17 Model of Main Fuel-to-NaK Heat E~changerC hannel 37
18 Prototype ART NaK-ta-Air Radiator 38
19 Plan of the ART Building 44
m Section of the ART Building 45
21 Reactor Assembly Cell 46
22 ART Shielding Experiment Facility 48
23 Pressure Load Distributions at Full Power 58
24 Conditions for Thermal @ye!i ng Tests of One-Fourth-Scale Model of 6Q
ART Core Shell in Comparison with ART Thermal-Cycling Conditions
25 ART Support Structure 62
26 Movement of Reactor Due ta Expansion of NQK tines 62
27 Layout of NaK Piping in Reactor Cell 63
<,-- 28 NaK-to-Air Radiator, NaK Pump, and NaK Piping External to Cell 64
29 65
ix
Figure No. Titie Page
30 Gamma-Ray Heating in he Vicinity of 64
on the Equatorial Plane of the ART
31 Heating in Copper-Boron Layer by Alpha Particles born the B”((n,Cr)Li7 48
Reaction
32 Configuration of ART North Head Showing Members Referred to in 69
Table 9
33 Total Power and Power Density in the Gas Space of the ART as a 70
Funetion of the Gas Volume and the Helium Flow Rete for B Fuel
Flow Rate of 22 gpm
34 Power Density in the Off-Gas bine as a Function of Time and Gas 71
Volume in the Expansion Tank for a Fuel Flow Rate of 22 gpm
35 North-Head Welderbil ity Model Showing Lower Deek and Peripheral Ring, 78
Step 1
36 North-Head Weidability Model, Step 2 78
37 North-Head Weldability Model, Step 3 79
38 North-Head Weldability Model, Step 4 79
39 North-Head Weldabil ity Model, Step 5 80
40 Narth-Head Weldability M~del,S tep 6 80
41 North-Head Weldability Model, Showing Ai=i~thetV- iew of Step 4 8’1
APPENDIX A
FLOW Diagram
1 Fuel Fif I-and-Drain, Enriching, Sampling, and Recovery Systems
2 Sodium System
3 Off-Gas System
4 Cel I Pumps Hydraul is Drive Systems
5 Reactsr Pumps Lube Oil System
6 Main, Auxiliary, and Special NaK Systems
7 NaK Pumps Lube Oil System
8 Process Air System
9 Pieiium System
10 Nitrogen System
’I1 Compressed Air System
12 Process water System
APPENDIX B
Figure No. Title Page
B. 1 -B.Q Photographs st Reactor Models 139- 144
B.7-B.33 Photographs of Stas? in the Construction of the ART Facility 145-171 \.A9
’” .
b....
X .- .