Extending CANTUP code analysis to probabilistic evaluations
Creators
- 1. Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (Romania)
Description
The structural analysis with numerical methods based on final element method plays at present a central role in evaluations and predictions of structural systems which require safety and reliable operation in aggressive environmental conditions. This is the case too for the CANDU - 600 fuel channel, where besides the corrosive and thermal aggression upon the Zr97.5Nb2.5 pressure tubes, a lasting irradiation adds which has marked consequences upon the materials properties evolution. This results in an unavoidable spreading in the materials properties in time, affected by high uncertainties. Consequently, the deterministic evaluation with computation codes based on finite element method are supplemented by statistic and probabilistic methods of evaluation of the response of structural components. This paper reports the works on extending the thermo-mechanical evaluation of the fuel channel components in the frame of probabilistic structure mechanics based on statistical methods and developed upon deterministic CANTUP code analyses. CANTUP code was adapted from LAHEY 77 platform onto Microsoft Developer Studio - Fortran Power Station 4.0 platform. To test the statistical evaluation of the creeping behaviour of pressure tube, the value of longitudinal elasticity modulus (Young) was used, as random variable, with a normal distribution around value, as used in deterministic analyses. The influence of the random quantity upon the hog and effective stress developed in the pressure tube for to time values, specific to primary and secondary creep was studied. The results obtained after a five year creep, corresponding to the secondary creep are presented
Availability note (English)
Available from author(s) or Institute for Nuclear Research - Pitesti, PO Box 78, RO-0300 Pitesti (RO). Fax 40-48-262449Additional details
Additional titles
- Original title (Romanian)
- Extinderea analizei cu codul CANTUP pentru evaluari probabilistice
Publishing Information
- Publisher
- Institute for Nuclear Research - Pitesti
- Imprint Place
- Pitesti (Romania)
- Imprint Title
- Nuclear Power - Current Status and Perspectives. INR 1971-2001 Symposium. Volume II
- Imprint Pagination
- 304 p.
- Journal Page Range
- p. 105-106
Conference
- Title
- Nuclear Power - Current Status and Perspectives. INR 1971-2001 Symposium
- Original Conference Title
- Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum II
- Dates
- 13 Jul 2001
- Place
- Pitesti (Romania)
INIS
- Country of Publication
- Romania
- Country of Input or Organization
- Romania
- INIS RN
- 32053755
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- C CODES; CANDU TYPE REACTORS; CREEP; FUEL CHANNELS; PRESSURE TUBES; PROBABILISTIC ESTIMATION; SWAGING; YOUNG MODULUS; ZIRCONIUM BASE ALLOYS
- Descriptors DEC
- ALLOYS; COMPUTER CODES; FABRICATION; HEAVY WATER MODERATED REACTORS; MATERIALS WORKING; MECHANICAL PROPERTIES; POWER REACTORS; PRESSURE TUBE REACTORS; REACTOR CHANNELS; REACTOR COMPONENTS; REACTORS; THERMAL REACTORS; TRANSITION ELEMENT ALLOYS; TUBES; ZIRCONIUM ALLOYS
Optional Information
- Notes
- 3 figs. Imprint:Conferinta ENERGETICA NUCLEARA - PREZENT SI VIITOR. ICN 1971-2001. Volum II