Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Ninth Quarterly Report, October-December 1963 Page: iii
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GEAP-4480
TABLE OF CONTENTS
Page Number
SECTION I
INTRODUCTION
1-1
SECTION II
SUMMARY
2-1
2. 1
Task B - Vented Fuel Development
2-1
2.2
Task C - Fuel Testing Ut TREAT
2-1
2.3
Task E - Fuel Performance Evaluation
2-1
2. 4
Task F - Fast Flux Irradiation of Fuel
2-2
2.5
Task G - Reactor Physics and Core Analysis
2-2
section m
TASK
B - VENTED FUEL DEVELOPMENT
3-1
3. 1
Sodium-Fuel Compatability
3-1
3.2
Fission Product Plugging
3-1
3.3
Fission Product Release
3-1
3.4
Fuel Operating Limits
3-5
SECTION IV
TASK
C - TRANSIENT TESTING OF FUEL
4-1
4 1
Series 2 - Unirradiated Mixed Oxide
4-15/4-16
4.2
Series 3 - Pre-Irradiated Mixed Oxide
4-15/4-16
4.3
Series 4 - Transient Clad Rupture or Penetration
4-9
SECTION V
TASK
E - FUEL PERFORMANCE EVALUATION
5-1
5. 1
Central Temperature Measurement of Mixed Oxide
Capsule E1A
5-1
5.2
High Burnup Irradiations
5-2
5.3
Plutonium Migration
5-5/5-6
5. 4
Fuel Compositions and Properties
5-11
SECTION VI
TASK
F - FAST FLUX IRRADIATION OF FUEL
6-1
6. 1
Irradiation in EBR-II
6-1
section vn
TASK
G - REACTOR PHYSICS AND CORE ANALYSIS
7-1
7. 1
U-238 - Pu-239 Resonance Overlap Effect
7-1
7.2
Physics Methods Development
7-3
7.3
FORE Code Modifications
7-5
7.4
The Effect of the Doppler Coefficient on the Meltdown
Accident in a Fast Reactor
7-5
REFERENCES
-1-
DISTRIBUTION
LIST
-4-
1 w •
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Leitz, F. J. Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Ninth Quarterly Report, October-December 1963, report, January 1964; San Jose, California. (https://digital.library.unt.edu/ark:/67531/metadc1201413/m1/2/: accessed July 17, 2024), University of North Texas Libraries, UNT Digital Library, https://digital.library.unt.edu; crediting UNT Libraries Government Documents Department.