Published 1978
| Version v1
Book
OCTAVIA: A computer code to calculate the probability of pressure vessel failure from pressure-transient occurrences
Creators
- 1. Nuclear Regulatory Commission, Washington, D.C. (USA)
Description
The OCTAVIA computer code has been developed to calculate the probability of pressure vessel failure from operationally caused pressure-transients which can occur in pressurized water reactors. The analysis approach is straightforward and involves calculation of vessel failure pressures using fracture mechanics methods and estimation of pressure-transient characteristics using historical, nuclear data. The Surry 1 pressure vessel is analysed to demonstrate the code's capabilities. For the exampled application, at an operating temperature of 1100F (430C), the vessel failure probability increases from 5x10-7 per reactor year at a vessel age of 2.5 years to 3x10-5 per reactor year at a vessel age of approximately 40 years. (author)
Additional details
Publishing Information
- Publisher
- IAEA.
- Imprint Place
- Vienna
- ISBN
- 92-0-050078-1
- Imprint Title
- Reliability problems of reactor pressure components
- Series
- Proceedings series.
- Journal Page Range
- v. 1 p. 105-122.
Conference
- Title
- Symposium on application of reliability technology to nuclear power plants.
- Dates
- 10 - 13 Oct 1977.
- Place
- Vienna, Austria.
INIS
- Country of Publication
- International Atomic Energy Agency (IAEA)
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 9386719
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- FAILURES; FRACTURE PROPERTIES; MATHEMATICAL MODELS; O CODES; PRESSURE VESSELS; PROBABILITY; SURRY-1 REACTOR; TEMPERATURE DEPENDENCE; TRANSIENTS
- Descriptors DEC
- COMPUTER CODES; CONTAINERS; ENRICHED URANIUM REACTORS; MECHANICAL PROPERTIES; POWER REACTORS; PWR TYPE REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- IAEA-SM--218/7.