Published 1977
| Version v1
Book
Fuel element design
Creators
- 1. Idaho National Engineering Lab., Idaho Falls (USA)
- 2. Cincinnati Univ., Ohio (USA)
Description
The in-reactor behavior of fuel-element materials is considered in this chapter. The application of the principles of mechanical analysis to fuel-element design is then examined in light of this behavior. Since uranium dioxide enriched with small amounts of either 235U or plutonium oxide and encapsulated in metal tubes is the predominant fuel of present power reactors, this consideration is limited to elements of this general type. (Auth.)
Additional details
Additional titles
- Subtitle (English)
- Chapter 11
Publishing Information
- Publisher
- Elsevier.
- Imprint Place
- Amsterdam, The Netherlands
- ISBN
- 0-444-41509-2
- Imprint Title
- Elements of nuclear reactor design
- Imprint Pagination
- p. 303-342.
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 8330842
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- CORROSION; CREEP; DEFORMATION; FUEL CANS; FUEL DENSIFICATION; FUEL ELEMENTS; FUEL PELLETS; FUEL-CLADDING INTERACTIONS; PHYSICAL RADIATION EFFECTS; STAINLESS STEELS; SWELLING; THERMAL EXPANSION; URANIUM DIOXIDE; ZIRCALOY
- Descriptors DEC
- ACTINIDE COMPOUNDS; ALLOYS; CARBON ADDITIONS; CHALCOGENIDES; CHEMICAL REACTIONS; CHROMIUM ALLOYS; CORROSION RESISTANT ALLOYS; EXPANSION; IRON ALLOYS; IRON BASE ALLOYS; MECHANICAL PROPERTIES; OXIDES; OXYGEN COMPOUNDS; RADIATION EFFECTS; REACTOR COMPONENTS; STEELS; TIN ALLOYS; TRANSITION ELEMENT ALLOYS; URANIUM COMPOUNDS; URANIUM OXIDES; ZIRCONIUM ALLOYS; ZIRCONIUM BASE ALLOYS