Published 1999
| Version v1
Report
Open
CKTI-Vibroseism study, parts I to IV
Description
This paper presents a summary of current earthquake design criteria used in former Soviet Regulations for equipment and piping systems of nuclear power plants in light of those used in United States and Japan. The detailed comparative seismic analysis of PWR (WWER) Primary Coolant Loop System (PCLS) according to Former Soviet (Russian) PNAE Code and ASME BPV Code with some comments regarding to Japan Code JEAG - 4601 was undertaken for better understanding of the differences and coincidences of seismic design criteria and requirements. The selection of these three guides for the study has very simple explanation: according to ASME BVPC, JEAG and PNAE the huge majority of existing NPPs has been designed
Files
30054696.pdf
Files
(1.2 MB)
| Name | Size | Download all |
|---|---|---|
|
md5:b469bc6d4d168a235b09873e29c31ce6
|
1.2 MB | Preview Download |
Additional details
Publishing Information
- Imprint Title
- Co-ordinated research programme on benchmark study for the seismic analysis and testing of WWER-type nuclear power plants. V. 2B. General material: codes, standards, criteria. Working material
- Imprint Pagination
- [111 p.]
- Journal Page Range
- [46 p.]
- Report number
- INIS-XA--199
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 30054696
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- A CODES; DESIGN; J CODES; P CODES; PRIMARY COOLANT CIRCUITS; REACTOR SAFETY; RISK ASSESSMENT; SEISMIC EFFECTS; SEISMIC EVENTS; SPECIFICATIONS; WWER TYPE REACTORS
- Descriptors DEC
- COMPUTER CODES; COOLING SYSTEMS; ENERGY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; PWR TYPE REACTORS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Refs, figs, tabs