Theory and verification manual for BARC-R6 software
Creators
- 1. Reactor Safety Div., Bhabha Atomic Research Centre, Mumbai (India)
Description
This report presents the technical description of the BARC-R6 computer code that has been developed in Reactor Safety Division, BARC. The program has been designed to run on Windows95 based PCs. The R6 method is a tool, which can perform analysis considering fracture and plastic instability together as failure criteria. The R6 method for analyzing flawed components requires construction of number of graphs. The results of study are arrived at by analyzing these graphs. BARC- R6 is designed with a highly intuitive graphical user interface for input as well as output. This report presents the implementation details of the program. The current version has provision for any flaw orientation and type in pipes and elbows. This program will be highly useful for fracture assessment and Leak Before Break (LBB) qualification for Nuclear Power Plant (NPP) piping. The complete PHT piping of any typical NPP can be assessed with in a very short time. It is capable of handling Option-1 and Option-2 Failure Assessment Line (FAL) for both Category-1 and Category-3 type analysis. It has provision for exhaustive sensitivity analyses for judging the significance of margins with respect to variation in material properties, crack sizes etc. The report is divided into 6 sections. The first section introduces the document. The details offer method are presented in the second section. This is followed by the technical description of the program. The fourth section lists many benchmark problems solved to highlight its usage and validation. These benchmark problems cover the wide range of cases encountered in the practical situations. The user manual is provided in the fifth section. The sixth section contains the references used in this report. This is followed by an appendix containing the co-relations for stress intensity factor and limit loads, used in the BARC-R6 code. (author)
Availability note (English)
Available from INIS in electronic formFiles
33012542.pdf
Files
(1.9 MB)
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Additional details
Publishing Information
- Imprint Pagination
- 96 p.
- Report number
- BARC--2001/E/001
INIS
- Country of Publication
- India
- Country of Input or Organization
- India
- INIS RN
- 33012542
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Descriptors DEI
- B CODES; BENCHMARKS; CRACKS; LEAKS; NUCLEAR POWER PLANTS; PIPELINES; REACTOR SAFETY; STRESS INTENSITY FACTORS; SYSTEM FAILURE ANALYSIS; VALIDATION
- Descriptors DEC
- COMPUTER CODES; NUCLEAR FACILITIES; POWER PLANTS; SAFETY; SYSTEMS ANALYSIS; TESTING; THERMAL POWER PLANTS
Optional Information
- Notes
- 4 refs., 26 figs., 1 ill.