Please use this identifier to cite or link to this item:
https://ptsldigital.ukm.my/jspui/handle/123456789/500284Full metadata record
| DC Field | Value | Language |
|---|---|---|
| dc.contributor.advisor | Faizal Mohamed, Assoc. Prof. Dr. | - |
| dc.contributor.author | Mazleha Maskin (P74119) | - |
| dc.date.accessioned | 2023-10-13T09:40:57Z | - |
| dc.date.available | 2023-10-13T09:40:57Z | - |
| dc.date.issued | 2018-06-07 | - |
| dc.identifier.other | ukmvital:114192 | - |
| dc.identifier.uri | https://ptsldigital.ukm.my/jspui/handle/123456789/500284 | - |
| dc.description | A level-I probabilistic safety assessment (PSA) for Puspati TRIGA nuclear reactor (RTP) has been develop. This includes a new list of postulated initiating events, new several components reliability data and a new development on plant-specific data procedure. Level-I PSA is specifically a failure model of the plant, which at the same time identifying accident progression scenario and estimating the likelihood of the scenario. Results for a level-I PSA is quantitatively presented as the core damage frequency (CDF). The main aim in this research is to assess the risk or safety component reliability of RTP by using Level 1 PSA model and at the same time to develop procedures for analysing plant-specific raw data. Accident sequences and system analysis were modelled using small event trees and large fault trees approach using Risk Spectrum® PSA software. Two sources of data were used, plant-specific and generic data. And both data were treated using first-stage Bayesian updates. The comprehensive analysis processes involved in this study are: identification and selection of important IEs, identification of core damage end-states, quantification of parameter estimation for both initial IEs and components, modelling of accident sequences and system analysis and development of a specific data procedure. Two main research outputs generated in this study are: (1) a complete step-by-step Level-1 PSA study for RTP; and (2) a procedure in collection, and interpretation, of specific information on component failure events, abnormal occurrences, and plant operational history consists of all related parameter estimation from the viewpoint of PSA needs. Results from this study conclude; seven most probable IEs for RTP were obtained using five systematic approaches and as a basis for the development of seven ETs which consists of 172 cases. Four core damage end-states were determined with most conservative assumptions, 34 FTs and list of minimal cut sets (MCS) are among the results from comprehensive studies mentioned earlier. In indicating how important each basic event in FTs, importance analysis was concluded to complement MCS-list. Finally, the value of interest, core damage frequency (CDF) was estimated to be 9.99x10 per reactor year, which is smaller than 10-4 , as per recommended by the IAEA standard criterion for PSA level-I. Procedures for developing specific raw data for a nuclear research reactor were successfully developed. This study provides input to decision makers on optimal strategies for reducing the levels of risk and at the same time provide information on accident consequences which will be imperative to operators if any abnormal events occurred. The development of plant-specific raw data procedure and availability of reliability data for specific systems components or basic events will facilitate other nuclear research facilities in developing their own level-I PSA as an important basis for conducting quantitative risk assessment for such a complex facility.,'Certification of Master's/Doctoral Thesis' is not available,Ph.D. | - |
| dc.language.iso | eng | - |
| dc.publisher | UKM, Bangi | - |
| dc.relation | Faculty of Science and Technology / Fakulti Sains dan Teknologi | - |
| dc.rights | UKM | - |
| dc.subject | System safety | - |
| dc.subject | Universiti Kebangsaan Malaysia -- Dissertations | - |
| dc.subject | Dissertations, Academic -- Malaysia | - |
| dc.title | The development of specific raw data procedure for level-I probabilistic safety assessment at Puspati TRIGA Reactor | - |
| dc.type | Theses | - |
| dc.format.pages | 217 | - |
| dc.identifier.callno | TA169.7.M339 2018 tesis | - |
| dc.identifier.barcode | 004345(2019) | - |
| Appears in Collections: | Faculty of Science and Technology / Fakulti Sains dan Teknologi | |
Files in This Item:
| File | Description | Size | Format | |
|---|---|---|---|---|
| ukmvital_114192+SOURCE1+SOURCE1.0.PDF Restricted Access | 1.54 MB | Adobe PDF |  View/Open |
Items in DSpace are protected by copyright, with all rights reserved, unless otherwise indicated.