Published 1987
| Version v1
Book
Experimental dynamic analysis of a manipulator crane and analytical prediction of results
Description
The governing loads taken into consideration in the design of the manipulator crane (i.e. the fuel loading machine) of a pressurized water reactor are seismic loads. Such loads are derived from a response spectrum analysis using a finite element model of the manipulator crane in a fuel loading position above the reactor vessel. In order to qualify the mathematical model of the manipulator crane used in this analysis, FRAMATOME and REEL have performed an experimental modal analysis of the crane for a four loop reactor. Experimental results are compared to calculated frequencies and mode shapes
Additional details
Publishing Information
- Publisher
- A.A. Balkema Publishers.
- Imprint Place
- Accord, MA (USA)
- ISBN
- 90-6191-772-7
- Imprint Title
- Structural mechanics in reactor technology
- Journal Page Range
- vp.
Conference
- Title
- international conference on structural mechanics in reactor technology.
- Acronym
- 9. SMIRT
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19084602
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- CRANES; DYNAMIC LOADS; EXPERIMENTAL DATA; FINITE ELEMENT METHOD; LOSS OF COOLANT; PRESSURE VESSELS; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; SEISMIC DETECTION; SPECIFICATIONS; STRESS ANALYSIS; TEST FACILITIES
- Descriptors DEC
- ACCIDENTS; CONTAINERS; DATA; DETECTION; ENRICHED URANIUM REACTORS; EQUIPMENT; INFORMATION; MATERIALS HANDLING EQUIPMENT; NUMERICAL DATA; NUMERICAL SOLUTION; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; REMOTE HANDLING EQUIPMENT; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS