Actions for Force analysis of the advanced neutron source control rod drive latch mechanism [electronic resource].
Force analysis of the advanced neutron source control rod drive latch mechanism [electronic resource].
- Published
- Washington, D.C : United States. Dept. of Energy. Office of Energy Research, 1989.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description
- Pages: (10 pages) : digital, PDF file
- Additional Creators
- Oak Ridge National Laboratory, United States. Department of Energy. Office of Energy Research, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The Advanced Neutron Source reactor (ANS), a proposed Department of Energy research reactor currently undergoing conceptual design at the Oak Ridge National Laboratory (ORNL), will generate a thermal neutron flux approximating 10³° M{sup −2}—S{sup −1}. The compact core necessary to produce this flux provides little space for the shim safety control rods, which are located in the central annulus of the core. Without proper control rod drive design, the control rod drive magnets (which hold the control rod latch in a ready-to-scram position) may be unable to support the required load due to their restricted size. This paper describes the force analysis performed on the control rod latch mechanism to determine the fraction of control rod weight transferred to the drive magnet. This information will be useful during latch, control rod drive and magnet design. 5 refs., 12 figs.
- Report Numbers
- E 1.99:conf-900143-2
conf-900143-2 - Subject(s)
- Other Subject(s)
- Reactor Control Systems
- Control Rod Drives
- Research And Test Reactors
- Castagnoli Formula
- Control Elements
- Design
- Dynamics
- Elasticity
- Finite Element Method
- Friction Factor
- Hfir Reactor
- Mathematical Models
- Measuring Methods
- Neutron Sources
- Ornl
- Performance Testing
- S Codes
- Stress Analysis
- Computer Codes
- Control Systems
- Enriched Uranium Reactors
- Irradiation Reactors
- Isotope Production Reactors
- Mechanical Properties
- Mechanics
- National Organizations
- Numerical Solution
- Particle Sources
- Radiation Sources
- Reactor Components
- Reactors
- Research Reactors
- Tank Type Reactors
- Tensile Properties
- Test Reactors
- Testing
- Thermal Reactors
- Us Aec
- Us Doe
- Us Erda
- Us Organizations
- Water Cooled Reactors
- Water Moderated Reactors
- Note
- Published through SciTech Connect.
01/01/1989.
"conf-900143-2"
"DE90003675"
Nuclear science symposium, San Francisco, CA (USA), 22-26 Jan 1990.
Damiano, B. - Funding Information
- AC05-84OR21400
View MARC record | catkey: 14361360