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Superphenix: Technical and Scientific Achievements 2017 ed. [Hardback]

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  • Format: Hardback, 342 pages, height x width: 254x178 mm, weight: 8635 g, 283 Illustrations, color; 59 Illustrations, black and white; XL, 342 p. 342 illus., 283 illus. in color., 1 Hardback
  • Pub. Date: 24-Jan-2017
  • Publisher: Atlantis Press (Zeger Karssen)
  • ISBN-10: 9462392455
  • ISBN-13: 9789462392458
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Superphenix: Technical and Scientific Achievements 2017 ed.Larger Image
  • Format: Hardback, 342 pages, height x width: 254x178 mm, weight: 8635 g, 283 Illustrations, color; 59 Illustrations, black and white; XL, 342 p. 342 illus., 283 illus. in color., 1 Hardback
  • Pub. Date: 24-Jan-2017
  • Publisher: Atlantis Press (Zeger Karssen)
  • ISBN-10: 9462392455
  • ISBN-13: 9789462392458
Other books in subject:
Permanent link: https://www.kriso.ee/db/9789462392458.html
Keywords:
For the first time a book has been written on the technological and scientific knowledge, acquired during, buiding , operation and even dismantling of the Superphenix plant. This reactor remains today the most powerful sodium fast breeder reactor operated in the world.(1200 MWe). The last fast breeder reactor operated in the world is BN 800 in Russia that reached his nominal power (800 MWe) in 2016.  Joel Guidez began his career in the field of sodium-cooled fast reactors after leaving Ecole Centrale-Paris, in 1973. He has held various positions at Cadarache, Phenix and Superphenix, including as the head of the thermal hydraulic laboratory conducting tests for Phenix, Superphenix and the EFR European Fast Reactor project. He was also head of the OSIRIS research reactor, located at SACLAY, and of the HFR European Commission reactor, located in the Netherlands and spent two years as nuclear attaché at the French embassyin Berlin. His 2012 book Phenix: the experience feedback was translated into English and republished in 2013, and this new book on Superphenix is in the same spirit of thematic analysis of a reactor experience feedback.





Gérard Prêle graduated from the Ecole Centrale-Lyon and entered EDF and the field of sodium-cooled fast reactors in 1983. In 1985 he joined Superphenix, where he was a duty engineer and was later in charge of safety. He has held various positions at Superphenix and Phenix and was a fast neutron reactor (SFR) engineer at the EDF Centre Lyonnais dIngénierie (CLI).  He worked  as Safety Security Environment and Radiation Protection Mission head in Superphenix  at the beginning of dismantling and then in the field of PWR for two years. Since 2006 he has been involved in the Gen IV and the SFR/Astrid projects. Today, as an SFR/system and operations expert, one of his major roles is assisting the CEA in the preliminary design of the ASTRID reactor.
1 General Description
1(22)
Introduction
1(1)
General Organization of a Sodium-Cooled Fast Reactor
1(1)
Superphenix Specific Case
2(1)
The Fuel Sub-assembly
2(2)
The Core
4(2)
The Reactor Block
6(2)
The Primary Circuit
8(2)
The Secondary Loops and the Electricity Generation
10(3)
The Auxiliary Circuits
13(1)
The Handling
13(3)
The Instrumentation and Control and Electrical Power Supply
16(2)
The Buildings
18(1)
Operating Mode
19(2)
References
21(2)
2 Construction Review
23(18)
A European Reactor
23(3)
General Organization
23(1)
Construction Site Beginning Date
24(1)
Industrial Organization
24(2)
The Overall Progress of the Reactor Block Construction Site
26(1)
The Fabrications in On-site Workshop for Large Diameter Structures
26(1)
Other Manufacturing and Exceptional Transports
26(1)
The Civil Engineering
27(1)
Reactor Block
27(1)
On-site Workshop
28(1)
The Manufacturing in the On-site Workshop
28(2)
The Notion of Package
28(1)
Manufacturing and Storage Methods
29(1)
The Package Transfer and Assembly in the Reactor Block
30(4)
First Package The Safety Vessel (260 t)
30(1)
Second Package The Main Vessel + The Core Catcher + The B1 Baffle (700 t)
30(1)
Third Package Conical and Toroidal Inner Vessels + Baffles + Chimneys + Pump Skirts (560 t)
31(1)
Fourth Package The Reactor Slab
31(1)
Main Vessel/Slab Welding
32(1)
Welding Safety Vessey/Slab
32(1)
Setting-up the Dead Body
33(1)
Setting-up the Dome Cylindrical Body
33(1)
Setting-up the Diagrid
33(1)
Setting-up the Rotating Plugs
33(1)
Setting-up the Dome (400 t)
33(1)
Setting-up the Storage Drum
34(1)
Works Finalization
34(1)
Works in the Plant "Conventional" Part
34(1)
The Schedule
35(1)
The Costs
36(2)
The Construction Costs
36(2)
Benchmarking with Water Reactors
38(1)
The Other Construction Sites
38(1)
Conclusion and Recommendations
39(1)
References
40(1)
3 Start-up Trials
41(10)
General Organization of Start-up Trials
41(1)
Phase 1 Subset Testing
41(1)
Phase 2 Filling-in with Sodium
42(1)
Phase 3 In-Sodium Isothermal Trials
42(1)
Phase 4 Rise to Rated Power
42(1)
Phase 1 Trials
42(1)
Progress
42(1)
Phase 1 Trial Results
43(1)
Phase 2 Trials
43(2)
Progress
43(1)
Phase 2 Trial Results
44(1)
Phase 3 Trials
45(1)
Progress
45(1)
Phase 3 Trial Results
45(1)
Phase 4 Trials
45(2)
Progress
45(1)
Phase 4 Trial Results
46(1)
Internal Structure Vibrations
47(2)
Reminders
47(1)
Vibrations Observed on the Reactor
47(1)
Analysis
47(1)
Solving the Problem
48(1)
Application to the Reactor and Consequence Analysis
48(1)
Partial Load Operations
49(1)
Conclusion
49(1)
Hydraulic and Thermal Hydraulic Trials
49(1)
Hydraulic Trials
49(1)
Thermal-Hydraulic Trials
49(1)
Conclusion and Recommendations
50(1)
Reference
50(1)
4 Objectives and Operation Results
51(10)
Introduction
52(1)
Superphenix Reactor Initial Objective
52(1)
The First Problems
52(1)
Situation in December 1986
53(1)
Operation/Shutdown Period Chronology
53(3)
First Operating Phase Untill the Storage Drum Leak
53(1)
Phase 2 83-EFPD Outage for Modifications Following the Storage Drum Unavailability
54(1)
Phase 3 Second Production Period Untill the 160-EFPD Outage
54(1)
Phase 4 Outage Period Until March 27, 1990
54(1)
Phase 5 Third Production Period from April to July 1990, Ended by the Air Ingress Incident
54(1)
Phase 6 Reactor Outage for Sodium Purification and Various Consequences up to 1994
55(1)
Phase 7 Re-start and Third Production Period
55(1)
Phase 8 Outage so as to Repair an Intermediate Heat Exchanger Seal Argon Supply
56(1)
Phase 9 Fourth and Final Production Period
56(1)
Phase 10 Definitive Shutdown
56(1)
Operation Review Results
56(1)
Objective Drift and Support Erosion
57(1)
Phenix and Superphenix: Technical Problem Comparison
58(1)
Conclusion
59(1)
References
60(1)
5 Safety
61(18)
The Safety Principles Applied During Initial Design
61(7)
Introduction
61(1)
Reactivity Control
62(1)
The Residual Power Removal
63(1)
Radioactive Product Containment
64(2)
Sodium-Related Protections
66(1)
The Containment Design Basis Accident (ADC)
67(1)
Conclusion
68(1)
Reactor Safety Review
68(2)
Safety During Operations
70(1)
Additional Procedures
70(1)
The State-Oriented Approach (APE)
71(1)
Probabilistic Safety Assessment (PSA)
71(1)
The Safety Requirement Evolutions During the Operating Period
71(5)
Spray Sodium Fires
72(1)
Gas Passing Through the Core
72(1)
Entire or Local Core Meltdown Scenarios (ULOF/BTI/RIB)
72(2)
Energy Released by a Sodium/Molten Core Interaction
74(1)
Making Reliable the Steam Generator Depressurization
75(1)
Sodium Aerosol Releases
75(1)
In-Service Inspection
75(1)
Conclusion
76(1)
Conclusions and Recommendations
76(1)
References
77(2)
6 Operating Experience
79(8)
Introduction
79(1)
Unavailability Review
79(2)
Attempt to Compare a PWR and Superphenix Operations
81(4)
Introduction
81(1)
Reactor Control
81(1)
The Core and the Fuel
82(1)
The Safety
82(1)
The Circuits
83(1)
The Fuel Handling
84(1)
Maintenance and Inspection
84(1)
Miscellaneous Points
85(1)
Conclusion and Recommendations
85(2)
7 Fuel Sub-assembly
87(10)
Introduction
87(1)
General Description
88(1)
Design Parameters
88(1)
Phenix Experience Feedback
88(1)
Detailed Description and Features
89(1)
The Upper Neutron Shielding
89(1)
The Hexagonal Tube
89(1)
The Pins
89(1)
The Pellets
89(1)
Sub-assembly Foot
90(1)
Connections Between Diagrid and Sub-assemblies, with Controlled Leaks
90(1)
Summary of the Main Features
90(1)
Manufacturing
90(3)
History
90(1)
Pellet Fabrication
91(1)
Sub-assembly Manufacturing
92(1)
Manufacturing Cost
93(1)
Conclusion
93(1)
Special Manufacturing
93(1)
Plutonium Isotopy
93(1)
Superphenix Fuel Validation Tests
93(2)
Operating Experience Feedback
95(1)
Grid Follow-up
95(1)
Conclusions and Recommendations for the Future
95(1)
References
96(1)
8 Neutronics
97(16)
Introduction
97(1)
Description of the Core
98(1)
Core Composition
98(1)
Enrichment Zones
98(1)
Management Mode
98(1)
Void Effect
99(1)
Core Monitoring and Control
99(2)
Neutron Monitoring
99(1)
Thermal Monitoring
99(1)
Clad Failure Detection and Location
100(1)
Flow Rate and Core Inlet Temperature Measurements
100(1)
"Scientific" Measurements
100(1)
Difficulties and Experience Feedback
101(1)
Loading the Core and Divergence
101(2)
The Trial Results from Start-up to Nominal Power
103(2)
Introduction
103(1)
Control Rod Negative Reactivity Value
103(1)
Feedback Coefficients
103(1)
Power and Flux Distribution
104(1)
Hydraulics and Thermo-hydraulics
104(1)
Control Rod Position
104(1)
Conclusions
105(1)
Core Follow-up During Reactor Operations
105(5)
Core Follow-up Methodology
105(1)
Zero-Power Trials
105(1)
In-Operations Monitoring
106(4)
Operating Experience
110(1)
General Experience
110(1)
Major Measurement Campaigns During Operations
110(1)
Conclusion
110(1)
Conclusions and Recommendations for the Future
111(1)
References
112(1)
9 The Primary Pumps
113(16)
Superphenix Primary Pump Features
113(3)
Functions
113(1)
General Description
114(1)
Main Dimensional Features
114(1)
Operating Conditions
115(1)
Instrumentation
115(1)
Inertia and Rotation Speed
115(1)
Hydrostatic Bearing Design
116(1)
In-Sodium Hydraulic Stream and Cavitation
116(1)
Shutter
117(1)
Shaft Line Sizing and Realization
118(1)
Taking-Over Expansions Between Slab and Junction with the Diagrid
118(1)
The Pump/Diagrid Link (LIPOSO) Tightness
119(2)
Promising Tracks that Did not Come to an End
121(1)
Ferrofluid Packing Boxes
121(1)
The Supercritical Shaft
122(1)
The Instrumentation
122(1)
The Materials
123(1)
Phenix Experience Feedback Integration
124(1)
Manufacturing
124(1)
In-Water Tests
125(1)
In-Reactor Operations
126(1)
Post Mortem Analyses
127(1)
Conclusions
127(1)
Proposals for the Future
127(1)
References
128(1)
10 Secondary Pumps and Circuits
129(8)
The Secondary Pump
129(2)
General Functions
129(1)
Pump Design Issues
129(1)
In-Water Tests at Gennevilliers
130(1)
Secondary Pump Description
130(1)
Secondary Pump Main Features
130(1)
Materials
131(1)
The Expansion Tank
131(1)
Expansion Tank Description
131(1)
Instrumentation
132(1)
Operating Experience Feedback
132(1)
Materials and Post-mortem Analysis
132(1)
The Sodium/Air Heat Exchanger
132(2)
Function
132(1)
Design
132(1)
Description
133(1)
Instrumentation
133(1)
Materials
133(1)
Main Features
133(1)
Operating Experience
134(1)
Isometry and Overall Organization of the Loop
134(1)
Piping and Overall Isometry
134(1)
Natural Convection Operations
134(1)
Experience Feedback
135(1)
Conclusion and Recommendations for the Future
135(2)
11 Intermediate Heat Exchangers
137(10)
Functions
137(1)
Description
138(1)
Characteristics and Operating Conditions
138(1)
Instrumentation
139(1)
Design Issues
139(1)
Phenix Experience Feedback on the Secondary Outlet Collector
139(1)
Seismic Resistance
140(1)
Thermosiphons
140(1)
Manufacturing and Controls
140(1)
Connections of Exchange Tubes to the Tube Plates
140(1)
Device to Soften the Collector Inner Shell
140(1)
Non accessible Welds
141(1)
Overall Control
141(1)
The Materials
141(1)
Test Review Before Introduction in Reactor
142(1)
Operating Experience
142(1)
Leak on the Exchanger Argon Seal
143(1)
Post-mortem Analyses
144(1)
Conclusions
145(1)
Recommendations for the Future
145(1)
References
146(1)
12 The Steam Generators
147(12)
Steam Generator Function
147(1)
Design Issues/Phenix Experience Feedback
147(1)
General Description
148(3)
Envelope
148(1)
Support Structure
148(1)
Sodium Circulation
149(1)
Tube Bundle/Support Structure
149(1)
The Tube Bundle
150(1)
Main Features
151(1)
Instrumentation
151(1)
Thermodynamics
151(1)
Level Measurements
151(1)
Sodium/Water Reaction Detection
151(1)
Sodium/Water Reaction
152(1)
Materials
152(1)
Adjustment and Qualification Tests
153(1)
Hydraulic Mockups
153(1)
Hydro-Elastic Mockups
153(1)
Mechanical and Thermo-mechanical Mockups
153(1)
Overall Mockups
153(1)
Conclusion on Tests
153(1)
Manufacturing and Control
154(1)
Tubes
154(1)
Outer Envelope
154(1)
Operating Experience
154(2)
Duration
154(1)
Start-up Test Results
155(1)
Transient Book Keeping and Monitoring
155(1)
Incidents
155(1)
Hydraulic Re-test
155(1)
Water Chemistry
155(1)
Conclusions
156(1)
Recommendations for the Future
156(1)
References
157(2)
13 The Sodium/Water Reactions
159(12)
Reminders on Sodium/Water Reactions
159(2)
Knowledge of Wastage Mechanisms
161(1)
Prevention of Sodium/Water Reactions
162(2)
Manufacturing
162(1)
Choice of Materials
163(1)
Design
163(1)
Detection
164(2)
Hydrogen Detection: Coexistence of in-Sodium and in-Argon Measurements
164(1)
Description of the BDH in-Sodium Hydrogen Detection System
164(1)
BDH Performances
164(1)
BDH Calibration
165(1)
BDD Detection
165(1)
Acoustic Detection (DA)
166(1)
Conclusion
166(1)
Mitigation
167(1)
Repair and Re-start
167(2)
Location of the Leak
167(1)
Identification of Weakened Tubes
168(1)
Repair Procedure
168(1)
Secondary Loop Reconditioning
168(1)
Conclusion
169(1)
Conclusions and Recommendations for the Future
169(1)
References
170(1)
14 Sodium Leaks and Fires
171(14)
Reminders on Sodium Fires
171(2)
Prevention
173(1)
Phenix Experience Feedback
173(1)
The Provisions Taken at Superphenix
173(1)
The Experience Feedback
174(1)
Conclusion
174(1)
Detection
174(4)
The Instrumentation
174(2)
The Under-Thermal-Insulation Leakage Issue
176(1)
The Spurious Alarm Issue
177(1)
Level Measurements
177(1)
The Staff
177(1)
The Experience Feedback on Leaks, Which Occurred
177(1)
Conclusions
177(1)
Mitigation
178(4)
Circuit Draining
178(1)
Choosing a Sizing Leak
178(1)
The Sodium Aerosol Release Issues in Accidental Situations
179(1)
The 1992--1994 Worksite
180(2)
Conclusions and Recommendations for the Future
182(1)
References
183(2)
15 Reactor Shutdown and Control Systems
185(12)
Introduction
185(1)
Phenix Experience Feedback
186(1)
Description of Superphenix Control Rods
186(3)
General Architecture
186(1)
Description of the Control Sub-assembly (Rod and Sheath)
187(1)
Absorbent Element Description
187(1)
Description of Rod Mechanisms
188(1)
The Back-up Shutdown System
189(1)
Validation Tests
189(1)
RBC Mechanisms
190(1)
Back-up Shutdown System
190(1)
Instrumentation and Control
190(2)
Operations with Power Setting
190(1)
Reactivity Control
191(1)
B4C Melting of a SAC Rod Issue During House Load Operation or Automatic Power Fallback Transients
192(1)
Experience Feedback
192(2)
Reliability
192(1)
Rod Worth
192(1)
SAC Spurious Falls
193(1)
RPRA and RPRB Experience Feedback
193(1)
House Load Operations or Automatic Power Fallback
193(1)
Improvements Brought up During Operations
193(1)
Lifetime
194(1)
Absorbent Dismantling
194(1)
Conclusions and Recommendations
194(1)
Reference
195(2)
16 Decay Heat Removal
197(10)
Introduction
198(1)
Reminders on the Decay Heat Removal Issues
198(1)
From Phenix to Superphenix: Design Evolutions
198(1)
Brief Description of Evacuation Circuits
199(1)
BPR
199(1)
RUR
199(1)
RUS
200(1)
Residual Power Measurement Trials at Superphenix
200(2)
Superphenix Decay Heat Removal Modes
202(1)
Removal Tests in Generalized Natural Convection
203(2)
Experience Feedback of RUR Residual Power Removal Circuits
205(1)
Conclusion and Recommendations for the Future
205(1)
References
206(1)
17 The Materials
207(14)
Reminders of the Material Operating Condition Specifities in a Sodium Fast Reactor
208(1)
Reminders of the Importance of the Manufacturing and Realization Quality
208(1)
Rapsodie/Phenix Experience Feedback and Related Choices for Superphenix Materials
209(1)
The Choices of Materials for Superphenix Structures and Components
210(4)
316L
210(1)
316 SPH
210(1)
304 L
211(1)
304 H
211(1)
800SPX Alloy
211(1)
15D3
212(1)
A 42/A 48
213(1)
10 CD 9-10 Low Alloy Steel
213(1)
CF3
213(1)
X20T3
214(1)
Fuel Sub-assembly Materials
214(1)
Fuel Cladding
214(1)
Hexagonal Tubes
214(1)
Conclusion on the Material Choices
214(1)
The Coatings
215(1)
Austenitic Steel Welding
215(1)
The Storage Drum Leak (See Chap. 22 "The Handling")
215(2)
Other Operating Experiences
217(1)
Fatigue Cracking
217(1)
Stress Caustic Corrosion Cracking
217(1)
Risk of Corrosion in the Drawdown Zone
217(1)
Extended Operation with High Oxygen Content
218(1)
Clad Failures
218(1)
Quality of Castings
218(1)
Conclusion
218(1)
«Post Mortem» Analysis Program
218(1)
The New Materials
218(1)
The Most "Loaded" Zones
218(1)
The Primary Pumps
218(1)
The Intermediate Heat Exchangers
219(1)
Sodium/Air Heat Exchangers of the Residual Power Removal Circuits (RUR)
219(1)
Steam Generators
219(1)
Secondary Loops
219(1)
Conclusions and Recommendations for the Future
219(1)
References
220(1)
18 Hydraulics and Thermo-hydraulics
221(14)
General Problems Posed by Thermo-hydraulics on Sodium Fast Neutron Reactors
222(1)
The Simulation Tools
222(2)
Introduction
222(1)
Water or Sodium?
222(1)
Hydraulics
223(1)
Stratification
224(1)
Gas Entrainment via Flows
224(1)
Conclusion
224(1)
The Reactor Block Sodium Thermo-hydraulics
224(4)
The Cold Pool
224(1)
The Hot Pool
225(3)
Conclusions
228(1)
The Reactor Block Gas Thermo-hydraulics
228(2)
Introduction
228(1)
Thermosiphons in Component Penetrations
229(1)
Heat Insulation in the Main Vessel On-Hold-Piece Zone
229(1)
Metallic Heat Insulation Between Main and Safety Vessels in On-Hold-Piece Zone
229(1)
Slab On-Hold-Piece Cooling Circuit
229(1)
Sodium Deposits
229(1)
Temperature Asymmetries on the Main Vessel In-Gas Part
230(1)
Conclusion
230(1)
The Components
230(1)
The Natural Convection
230(1)
Natural Convection on Primary Side
230(1)
Natural Convection on Secondary Side
231(1)
Conclusion
231(1)
Gas Being Entrained by Sodium
231(2)
Argon Being Entrained in Nominal Conditions
231(1)
Phenix Negative Reactivity Scrams and the Consequences for Superphenix
232(1)
Conclusions and Recommendations for the Future
233(1)
References
234(1)
19 In-Service Inspection
235(16)
Introduction
235(1)
Definition of the Major In-Service Inspections
236(3)
Main Vessel
236(1)
Safety Vessel
237(1)
Slab
237(1)
Core Support Plate
237(1)
Diagrid and Diagrid Support
237(1)
LIPOSO (Pump-Diagrid Link)
238(1)
Internal Vessels
238(1)
BCC (Core Cover Plug)
238(1)
Rotating Plugs
238(1)
Components
238(1)
Studied Solutions but that Remained at a Study State
238(1)
Conclusion
239(1)
Experience Feedback of the Major In-Service Inspections Carried Out During the Reactor Life
239(8)
Inspection of Superphenix Vessels
239(2)
Triple Point Control
241(1)
Core Cover Visual Inspection
242(1)
Controlling the Position of the Core Support Structure
243(1)
Studies so as to Know the Reactor Upper Closure Sealing
243(1)
Ultrasonic Testing of Steam Generator Tubes
243(3)
Steam Generator Hydraulic Tests
246(1)
Miscellaneous
247(1)
Conclusion
247(1)
Transient Book Keeping and Monitoring
247(2)
Manufacturing Quality Review
249(1)
Conclusions and Recommendations for the Future
249(1)
References
250(1)
20 The Chemistry
251(20)
Consequences of the Sodium Chemical Properties
252(1)
Application of Phenix Experience Feedback
252(1)
Superphenix Sodium Monitoring and Control Systems
253(4)
The Plugging Indicators
253(2)
The Purification System (Cold Trap)
255(1)
The Hydrogen Detections
256(1)
TASTENA Sampling
256(1)
The Start-up External Purification Unit
256(1)
Filling-in the Reactor and Start-up Purification
257(1)
Primary and Secondary Sodium Activation
258(1)
Primary Circuit Pollution Incident
259(2)
Incident Progress
259(1)
Purification Campaigns
259(1)
Incident Consequences
259(1)
Lessons and Corrective Actions
260(1)
Cold Trap Operating Experience and Developments
261(2)
Driving Rules
261(1)
Cold Trap Infilling Follow-up
261(1)
Cold Trap or Cartridge Lifetime Before Plugging
262(1)
In-Operations Feedback
262(1)
Review of Used Cartridges
263(1)
Trapping Tritium
263(1)
Corrosion and Mass Transfers
264(1)
Corrosion
264(1)
Activation of Corrosion Products
265(1)
Quantifying Corrosion and Deposits
265(1)
Sub-assembly Dripping-Washing
265(1)
The Water Chemistry
266(1)
Conclusion and Recomendations
266(2)
References
268(3)
21 The Sodium Technology
271(12)
Introduction
271(1)
Reminder of Some Sodium Properties
272(1)
A Metallic Fluid
272(1)
Austenitic Steel Difficult Tribology
272(1)
A Solidification Below 98°C
272(1)
Tendencies to Thermal Stripping
272(1)
Sodium Valves
272(3)
Precautions of Use
274(1)
Experience Feedback
274(1)
Conclusion
275(1)
Electromagnetic Pumps
275(1)
Precautions of Use
275(1)
Experience Feedback
275(1)
Conclusion
276(1)
Measurement Instrumentation
276(2)
Temperature
276(1)
Level Measurements
276(1)
Pressure Measurements
276(1)
Flow Rate Measurements
277(1)
Miscellaneous
277(1)
Sodium Circuits
278(1)
Thermal Stripping and Mixers
278(1)
Piping Support Structures
278(1)
Storage Tanks
278(1)
Argon Circuits
279(1)
Equipment Using NaK
279(1)
Wetting and Tribology
280(1)
Mechanical Problems Occurred on the Clad Failure Detection and Location Modules (RGS and RGR)
281(1)
Conclusions and Recommendations
281(1)
Reference
282(1)
22 The Handling
283(18)
General Description of Superphenix Initial Handling System
284(3)
Phenix Experience Feedback
284(1)
Circuit Functions
284(1)
Operating Conditions
284(1)
Fresh Sub-assembly Pathway
285(1)
Irradiated Sub-assembly Pathway
286(1)
Brief Description of the In-Sodium Handling Chain Main Components (Primary Handling)
287(1)
Rotating Transfer Lock and Inclined Ramps
287(2)
Transfer Machines
287(1)
Storage Drum
288(1)
Operating Experience Feedback with Storage Drum Available
289(1)
Operating Results
289(2)
Encountered Difficulties
290(1)
Conclusion
291(1)
Incident of the Storage Drum Leak and Change of the Handling Chain
291(1)
The Incident Progress
291(2)
Switching to an in-Gas Handling
292(1)
Transfer Time Maximum Durations
292(1)
Other Consequences
293(1)
The In-Gas Handling Campaign Experience Feedback
293(3)
The Context
293(1)
The Optimization of the Core Sub-assembly and Element Washing
293(1)
The Campaign Progress
294(1)
Encountered Difficulties
294(1)
Conclusion on the Rates
295(1)
Special Handlings
296(2)
Principle and Description
296(1)
Operations Mode
296(1)
Experience Feedback
297(1)
Conclusions and Recommendations for the Future
298(1)
References
299(2)
23 The Environmental Results
301(10)
Introduction
301(1)
Reminder of the Contamination Sources
302(1)
Fuel
302(1)
Sodium Activation
302(1)
Activation of Impurities Contained in the Sodium
302(1)
Structure Activation
303(1)
Activation Products Present in the Core Cover Gas
303(1)
The Gaseous Releases
303(1)
The Case of Tritium
304(2)
Source Calculation
304(1)
Tritium Behaviour in the Circuits
304(1)
Measurements
304(1)
Estimates After Shutdown
305(1)
Estimates of Tritium Releases During "Washing"
305(1)
The Liquid Waste
306(1)
Irradiated Sub-assembly Washing
306(1)
Component Washing
306(1)
The Solid Waste
306(1)
Conventional Waste
307(1)
Radioactive Waste
307(1)
Chemical Releases
307(1)
The Thermal Releases
308(1)
The Dosimetry
308(1)
Conclusion and Recommendations
308(2)
References
310(1)
24 The Dismantling
311(12)
Introduction
311(1)
International Experience for Sodium-Cooled Fast Reactor Dismantling
311(3)
US Reactors: EBR1, EBR2, EFFBR (FERMT-1), FFTF
312(1)
United Kingdom Reactors: PFR and DFR
312(1)
The Soviet-Designed Reactors: BOR 10 and BN350
312(1)
KNK II German Reactor
313(1)
The French Reactor Rapsodie
313(1)
Conclusion
314(1)
Superphenix Operation Progress
314(4)
Phase 1
314(1)
Phase 2
315(1)
Phase 3
316(1)
Phase 4
316(1)
Phase 5
316(1)
Phase 6
317(1)
Phase 7
318(1)
A Fast Reactor Dismantling General Specificities
318(2)
Sub-assembly Washing
318(1)
Keeping Sodium Under Liquid Form
318(1)
Getting Out Removable Components
318(1)
Provisions for Cold Traps Containing Active Products
318(1)
Sodium Processing
319(1)
Processing of All the Circuits Having Contained Sodium
319(1)
NaK Processing
320(1)
Reminder of the Difficulties and Necessary Developments
320(2)
Sodium Residual Volumes in the Reactor Block
320(1)
Control Rods
320(1)
Cold Traps
321(1)
Activity Level
321(1)
Tritium
321(1)
MESOS
321(1)
Dismantling Environmental impacts
322(1)
Recommendations for the Design of Future Reactors
322(1)
Materials
322(1)
Accessibility to PNL (Lateral Neutron Shielding)
322(1)
Reactor Block Draining Capacity
322(1)
Minimization of Aerosol Deposits
322(1)
Avoid the Use of NaK
322(1)
Waste Zoning
323(1)
Tritium
323(1)
Primary Cold Traps
323(1)
Various Cold Trap or Their Cartridge Processing
323(1)
Control Rods
323(1)
References
323(1)
25 Superphenix Children
323(14)
Introduction
323(1)
Reminder of the Major Design Changes Between Phenix and Superphenix
324(1)
Design Evolution from Superphenix to SPX2
325(5)
Introduction
325(1)
Core and Sub-assemblies
325(1)
The Reactor Block
326(1)
The Large Components
327(2)
The Fuel Handling
329(1)
Conclusion/Weight and Cost Savings
329(1)
From SPX2 to EFR
330(2)
Introduction
330(1)
External Contributions from Partners
330(1)
Optimizing the Number of Loops
330(1)
The Core
330(1)
The Reactor Block
330(2)
Residual Power Removal
332(1)
The Reactor Building
332(1)
Conclusion and Results
332(1)
The Safety Evolution from Superphenix to EFR
332(2)
Conclusion and Recommendations
334(1)
References
335(2)
26 Conclusion
337
An Almost Unlimited Energy for the Planet with SFR Technology
337(1)
Interesting Environmental Results
338(1)
A Minimization of Final Waste in Quantity and Dangerousness
338(1)
Real Scientific Achievements for the Future
338(1)
An Opening on the Future
339(1)
A Permanent Challenge
339(1)
Reference
340