ML19347A382
| ML19347A382 | |
| Person / Time | |
|---|---|
| Site: | University of Buffalo |
| Issue date: | 09/23/1963 |
| From: | NEW YORK, STATE UNIV. OF, BUFFALO, NY |
| To: | |
| References | |
| NUDOCS 8104080560 | |
| Download: ML19347A382 (5) | |
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TABLE CF CCurdNr3 Page I.
INTRODUCTION.......................................
1 II. 14 CATION..........................................
1 1
A. C. _ u..................................
1 B.
Site.....................................
2 C.
!kterology...............................
5 1
Temperature........................
6 2
Uinds..............................
11
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3.
Precipit,' ion......................
20 D.
Hydrology................................
26 1.
Concrci............................
26 2
Geolony............................
26 I
3.
Soil Characteri stics...............
27 4.
Conclusions........................
31 m "
E.
Seisamlogy...............................
31 III. LE.*.CTOR BUILDI NG...................................
33 A. Genera 1..................................
33 B.
Neutron Deck level.......................
34 C.
Coma Deck Leve l.........................
35 D. Control Deck Level.......................
35 E
E.
Has te Dis pos al...........................
40
,J, F.
Monitoring of Air Discharge..............
40 IV. REACTOR DES CRIPTION...............................
43
- ~
A.
General..................................
43
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- 3. Reactor Tank.............................
44 C.
Core and Supporting Structure............
45 D.
Fuel.....................................
47 i
E.
Cooling and Purification.................
49 F.
Shim Safety Rods and Drives..............
51 j
1 Shim Safety and Regule.
cing S afety nods.................
51 i
2 Transient Rod......................
53 i
G.
Instrumentation..........................
53
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1 Steady Stata Operation.............
53
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(a) Count-Rate or Start-up Channel.......................
55 (b) Linear N Power................
55 (c) Ing N Pouer Channel...........
55 (d ) S afety Channels................
56 (e) Temperatures...................
57 2
Transient operation.................
50 j
3.
Radiation Monitors..................
61 4
Mtsse11aneous.......................
62 N
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- H It TABLE OF CONTENTS (Cont'd)
_o 1!. Expo:icental Pacilitics......................
65 1
Core Expe ri ments.....................
65
~ 7 2
Dcam Tubes.............................
65 w
3.
ncbbit Tubes...........................
65 4.
Th e rma l Co lumn.........................
65 5.
Caus Faci li ty.........................
66 6
Hedical Facility.......................
66 7.
Hot Ce11...............................
68 C.
Fission Plate..........................
60 l
I.
E::periment al Pro 3 ram.........................
68 i
J.
Reactor Operation............................
70 1
Initial Start-up and Approach to Cri ticali ty.......................
70 w
2 Normal Operation St art-up..............
71 t
(a) Steady State Operation............
71
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(b ) Puls e Operation...................
72
-g '"
V.
REACTIVITY n5UIREHENTS...............................
74 m
A.
Temperature coefficient......................
75 n.
In-Core Experimento..........................
75 C.
Ecsm Tubes and Pneumatic Conveyors...........
75 D.
Eurn-up and Low Cross Section Fission.
Products....................................
75 E.
Equi librium Xenon............................
76 F.
Parti al S amarium...........'..................
76 C.
Power Coe f fi ci e nt............................
76 H.
The rma l Co lumn...............................
76
.m I.
Puls e Reac tivity Raquirements................
76
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J.
Long Team Operation..........................
77 K.
Typical Core Loading.........................
77 l
VI. PERSONNEL AND ORGANIZATION...............'.............
79
.ns VII.HA2ARDS...............................................
80 A.
Natural Hazards..............................
81 B.
Hinor Accidents..............................
81 1
Loss of Ventilation....................
81 2
Coolant Pump Failure...................
83 3.
Wate r-logging..........................
03 4.
Loss of Pool Water.....................
35
.I' S.
Heximus Start-up Accident..............
85 le 6
Transient Rod Foils to Return to Starting Position.....................
07 C.
Ha::imum Credible Accident....................
88 l w 1
Cause..................................
80 l
2 Resu l t s................................
91 l
(a) Release of 3.5 per cent luff......
94 (b) Continuous nelease................
90 ll" (c) Hasards Ulthin the Reactor l g.
E Building.........................
101 (d) External Hazards..................
103 l lw
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TABIE OF CONTENTS (Cont'd)
Pane
- 3. Conclusion.............................
104 APPENDIX I................................................
105 A.
Phycies.............................
105 1.
Steady State...........................
105 2.
Transient..............................
110
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D.
Re ac t ivi ty E f fe c t s...........................
112
' j 1.
k na Torm Operations...................
112
- 5 2.
Xenon and Samariun Poisoning...........
117
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3.
Control Rod Worth......................
120 J
C.
Flux De te rminat io n...........................
123 3
1.
Steady state...........................
123 2.
Transient..............................
127 D.
Heat Trans fer and Stress Analysis............
133 1.
Steady Stato...........................
133
- 2. Transient..............................
149 3.
Stress Analysis........................
150
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'l LIST OF FICITdES ILLUSTMATIONS, AND GRAPHS
,l
,5 Subject Pace No.
Finure No.
I Geological Survoy Map of Duffalo and Vicinity 3
I II Aarial View of Campus and Area to Se.cbeast 4
III Graph of Seasonal Variation of Lapse Rate 8
(1890 to 1930)
IV, V VI Wind Roso Diag ses Shoving Direc6n and Velocity 13, 14,14A
)
Avorago Monthly Values (1918 - 1947)
VII Geological Profile of Campus in North-South 28 I
Direction VIII Strati rophic Column at Nuclear Reactor Sito 29 d
II Roactor Building - Basement Plan (Neutron Deck) 36 X
Reactor Building - First Floor Plan (Cascoa Deck) 37
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XI Reactor Building - Second Floor Plan (Control 38 Dock) 95 8h XII Reactor Building - Cross Section at Centerline 39 4
i of Reactor, and Longitudinal Section at i
Contarline of Building XIII Plenum Safety Flapper and Grid Plata Assembly 46 XIV APR Fuct Assembly 48 XV Cooling and Purification ' System 50 XVI Pulse Rod Mechanism 54 XVII Block Diagram of Nuclear Reactor 59, 60 i
XVIII Vertical Section Through Thermal Column 67
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).'I LI
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LIST OF FIGURES ( Cont'd)
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.w I
Finuro No.
Subicet Pane No.
==d A-1 K,gg vs. Mw Days 115 A-2 B
vs. Burnup 116 1
i A-3 Pu-239 Inventory at 2 Hv Operati: n 118 l
A-4 Xonon Buildup vs. Tha after Startup 119 A-5 Xenon Poisoning, vs. Tirsa After Shutdown 119A
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A-6 Integral Rod Worth 122 T
A-7 Flux Traverse Across Core and Reflector 124
.a A-8 Flux in Reflector 125
.j A-9 Flux in Reflector 126 A-10 Flux in Wsterhole at Center of Core 128 A-11 Flux in Waterhole at Center of Core 129 7
A-12 Flux in U-Shaped Cavity 130
,.4 A-13 Flux in U-Shaped Cavity 131 A-14 AG Steady State Tempcrature Diitribution at 2 Hw 140 A-15 Power Input - 40 Mw-sec Pulse 142
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A-16 Power Input - 90 Mw-sec Pulse 143 A-17 Fuel Pia Radial Power Distribution 144 A-18 Specific Beat - U0 145 2
A-19 Thermal Conductivity - UO 146 2
A-20 Thermal Diffusivity of 00 and Zr 147 2
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A-21 APR Fuel Pin 148 A-22 Temperature variation for U0 and Zr 151 2
Natural Convection A-23 Ibermal Stress vs. Temperature Difference 155 Across Clad A-24 Yiold Strength of Zircaloy-2, Variation of 156 Young's Modulus with Tamperature l
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