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pro vyhledávání: '"Richard Trewin"'
Autor:
Richard Trewin
Publikováno v:
Nuclear Technology. 208:860-870
Publikováno v:
Nuclear Science and Technology. 7:1-7
The Best-Estimate Plus Uncertainty (BEPU) is applied as Deterministic Approach for safety analysis of Nuclear Power Plant using the system analysis code. The system analysis code such as Relap5/Mod3.3 is required to be able to simulate the thermal-hy
Publikováno v:
Volume 6A: Materials and Fabrication.
The integrity of a reactor pressure vessel (RPV) has to be ensured throughout its entire life in accordance with the applicable regulations. Typically an assessment of the RPV against brittle failure needs to be conducted by taking into account all p
Autor:
Richard Trewin
Publikováno v:
Nuclear Engineering and Design. 374:111027
Using closed thermosiphons for cooling the spent-fuel pools of nuclear power plants requires calculation tools for simulating the thermal performance of long thermosiphons. The ability of the computer program THERESA to simulate the thermal performan
Publikováno v:
Nuclear Engineering and Design. 355:110282
Pressurized thermal shock (PTS) is the stress experienced by a reactor pressure vessel (RPV) due to a rapid temperature and pressure change, or large spatial variations in temperature because of plumes and stripes of cold water surrounded by hotter w
Autor:
Markus Niffenegger, Guian Qian, Ralf Tiete, Vladislav Pistora, Sébastien Blasset, Miroslav Posta, Richard Trewin
Publikováno v:
Volume 6A: Materials and Fabrication.
In this paper the project DEFI-PROSAFE is presented. In the frame of Nugenia+ project, a work package was dedicated to the “DEFInition of reference case studies for harmonized PRObabilistic evaluation of SAFEty margins in integrity assessment for l
Publikováno v:
Volume 6A: Materials and Fabrication.
The integrity of a reactor pressure vessel (RPV) has to be ensured throughout its entire life in accordance with the applicable regulations. Typically an assessment of the RPV against brittle failure needs to be conducted by taking into account all p
Autor:
Richard Trewin
Publikováno v:
Nuclear Engineering and Design. 241:2470-2483
A one-dimensional three-field model was developed to predict the flow of liquid and vapor that results from countercurrent flow of water injected into the hot leg of a PWR and the oncoming steam flowing from the upper plenum. The model solves the con
Publikováno v:
Proceeding of International Heat Transfer Conference 10.
Publikováno v:
Scopus-Elsevier
Richard R Trewin
Richard R Trewin
Externí odkaz:
https://explore.openaire.eu/search/publication?articleId=dedup_wf_001::3dc23b0c3e6538af5dde1b5671ef5454
http://www.scopus.com/inward/record.url?eid=2-s2.0-0026992407&partnerID=MN8TOARS
http://www.scopus.com/inward/record.url?eid=2-s2.0-0026992407&partnerID=MN8TOARS