Fuel Management Strategies for Pressurized Water Reactors
Author: William Thomas Miles
Publisher:
Published: 1973
Total Pages: 236
ISBN-13:
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Author: William Thomas Miles
Publisher:
Published: 1973
Total Pages: 236
ISBN-13:
DOWNLOAD EBOOKAuthor: Edward Alfred Starbird
Publisher:
Published: 1970
Total Pages: 496
ISBN-13:
DOWNLOAD EBOOKAuthor: Frederic Kolenda
Publisher:
Published: 1982
Total Pages: 374
ISBN-13:
DOWNLOAD EBOOKAuthor: Shafiq Y. Hurani
Publisher:
Published: 1980
Total Pages: 198
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DOWNLOAD EBOOKAuthor: Michael John Cenko
Publisher:
Published: 1975
Total Pages: 160
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DOWNLOAD EBOOKAuthor: Lance Neville Otis
Publisher:
Published: 1970
Total Pages: 336
ISBN-13:
DOWNLOAD EBOOKAuthor:
Publisher:
Published: 1964
Total Pages:
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DOWNLOAD EBOOKEconomic and operational ground rules and their effects on fuel management are summarized, and examples showing the approach to typical fuel management problems are presented. The problems associated with in-core fuel management are also discussed, and the merits of various fuel cycling methods are evaluated. (D.C.W.).
Author: Harvey W. Graves
Publisher: John Wiley & Sons
Published: 1979
Total Pages: 360
ISBN-13:
DOWNLOAD EBOOKAuthor: Joseph A. Sefcik
Publisher:
Published: 1981
Total Pages: 241
ISBN-13:
DOWNLOAD EBOOKSystematic procedures have been devised and applied to evaluate core design and fuel management strategies for improving uranium utilization in Pressurized Water Reactors operated on a once-through fuel cycle. A principal objective has been the evaluation of suggested improvements on a self-consistent basis, allowing for concurrent changes in dependent variables such as core leakage and batch power histories, which might otherwise obscure the sometimes subtle effects of interest. Two levels of evaluation have been devised: a simple but accurate analytic model based on the observed linear variations in assembly reactivity as a function of burnup; and a numerical approach, embodied in a computer program, which relaxes this assumption and combines it with empirical prescriptions for assembly (or batch) power as a function of reactivity, and core leakage as a function of peripheral assembly power. State-of-the-art physics methods, such as PDQ-7, were used to verify and supplement these techniques. These methods have been applied to evaluate several suggested improvements: (1) axial blankets of low-enriched or depleted uranium, and of beryllium metal, (2) radial natural uranium blankets, (3) low-leakage radial fuel management, (4) high burnup fuels, (5) optimized H/U atom ratio, (6) annular fuel, and (7) mechanical spectral shift (i.e. variable fuel-to-moderator ratio) concepts such as those involving pin pulling and bundle reconstitution. The potential savings in uranium requirements compared to current practice were found to be as follows: (1) O0-3%, (2) negative, (3) 2-3%; possibly 5%, (4) "15%, (5) 0-2.5%, (6) no inherent advantage, (7) 10%. Total savings should not be assumed to be additive; and thermal/hydraulic or mechanical design restrictions may preclude full realization of some of the potential improvements.
Author: Leancy Giovanni Lobo
Publisher:
Published: 1980
Total Pages: 432
ISBN-13:
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