Published 1978 | Version v1
Book

OCTAVIA: A computer code to calculate the probability of pressure vessel failure from pressure-transient occurrences

  • 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.