Analysis of forces on core structures during a loss-of-coolant accident. Final report
Description
There are several design requirements related to the emergency core cooling which would follow a hypothetical loss-of-coolant accident (LOCA). One of these requirements is that the core must retain a coolable geometry throughout the accident. A possible cause of core damage leading to an uncoolable geometry is the action of forces on the core and associated support structures during the very early (blowdown) stage of the LOCA. An equally unsatisfactory design result would occur if calculated deformations and failures were so extensive that the geometry used for calculating the next stages of the LOCA (refill and reflood) could not be known reasonably well. Subsidiary questions involve damage preventing the operation of control assemblies and loss of integrity of other needed safety systems. A reliable method of calculating these forces is therefore an important part of LOCA analysis. These concerns provided the motivation for the study. The general objective of the study was to review the state-of-the-art in LOCA force determination. Specific objectives were: (1) determine state-of-the-art by reviewing current (and projected near future) techniques for LOCA force determination, and (2) consider each of the major assumptions involved in force determination and make a qualitative assessment of their validity
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS., PC A07/MF A01.
Files
Additional details
Publishing Information
- Imprint Pagination
- 130 p.
- Report number
- PB--81-140428
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 13702747
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BLOWDOWN; DEFORMATION; DYNAMIC LOADS; FLUID FLOW; GEOMETRY; HYDRAULICS; LOSS OF COOLANT; MOTION; REACTOR CORES; THERMODYNAMIC PROPERTIES; WATER COOLED REACTORS
- Descriptors DEC
- ACCIDENTS; MATHEMATICS; PHYSICAL PROPERTIES; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS