[PDF] Top 20 Leak before break demonstrations for Sodium Fast Reactors
Has 10000 "Leak before break demonstrations for Sodium Fast Reactors" found on our website. Below are the top 20 most common "Leak before break demonstrations for Sodium Fast Reactors".
Leak before break demonstrations for Sodium Fast Reactors
... For an actual TWC (under creep-fatigue), a rather good agreement with experimental results has been obtained by using the RCC-MRx Appendix A16 LBB's procedure, the leak rate being calcu[r] ... See full document
10
Leak Before Break Investigation on Sodium Piping for Prototype Fast Breeder Reactor (G335)
... The largest Tee adopted for the secondary sodium circuit of PFBR is considered for the investigation. The nominal dimensions of the run pipe are 800 mm diameter and 18 mm wall thickness. The corresponding values ... See full document
7
Improvement of leak-before-break methodology for Sodium Fast Reactors
... The crack-opening-displacement is calculated from the minimal size (L2) of the crack. This assumption leads to underestimating the crack-opening area, and consequently the leak rate. An equivalent crack length ... See full document
10
Leak Before Break Procedure for High Temperature Reactors and Gas Fast Reactors - Crack Opening Profile Studies for Complex-Shaped Defects in Thick Components
... The main result is that, whatever the configuration and the defect size, the current A16 method leads to an important underestimation of the crack opening at the small breach, e.g. at the outer skin, where the detection ... See full document
8
Demonstration of leak-before-break in Japan sodium cooled fast reactor (JSFR) pipe
... The authors proposed an elasto-plastic COD assessment method applicable to thin wall pipes with large diameter made of modified 9Cr-1Mo steel [4] based on the conventional GE/EPRI method [5]. Parametric finite element ... See full document
8
Leak-Before-Break Assessment of RBMK-1500 Fuel Channel in Case of Delayed Hydride Cracking (G178)
... For leak rate calculations the computer program SQUIRT ...of leak rate, the numbers of turns (CPL – Coefficient of Path Loss) equal to 3 for one rib were ...the leak rate rapidly increases, when the ... See full document
8
Review of safety improvement on sodium cooled fast reactors after Fukushima accident
... Several countries are developing and deploying SFRs even after the accident at Tokyo Electric Power Company’s Fukushima Dai-Ichi Nuclear Power Station. However, the Fukushima acci- dent prompted all countries to redefine ... See full document
7
Applicability of LBB (Leak-Before-Break) Design for Main Steam Line in Korea Nuclear Power Plant
... LBB design for main steam line in nuclear power plant, by changing the material of MSL piping in. direction of increasing the toughness and using the additional [r] ... See full document
7
Evaluation of leakage size crack for leak-before-break assessment considering piping system compliance
... Leak-before-break (LBB) has been widely accepted as a technical approach to eliminate pipe- whip restraints and jet-impingement shields in many nuclear power plants (NPPs). Concerns related to the ... See full document
7
Development of the Technical Basis for a New Regulatory Guide for Leak-Before-Break (LBB) Applications (G411)
... advanced leak-rate or fracture mechanics codes. In lieu of the use of leak-rate codes for predicting the postulated leakage flaw size, a series of simple, empirically-derived influence functions were ... See full document
8
Nuclear data sensitivity and uncertainty assessment of sodium voiding reactivity coefficients of an ASTRID-like sodium fast reactor
... the sodium cooled fast reactor technology is ASTRID (standing for Advanced Sodium Technological Reactor for Industrial Demonstration), which detailed design phase is foreseen to be initiated in ... See full document
6
OPERATION OF NUCLEAR POWER STATIONS IN 1990. Theme 4, Series C. MAY 1991
... Installed capacity Maximum output capacity of which : Gas cooled reactors Advanced gas cooled reactors Light water reactors Fast reactors Others PERFORMANCES * Mean energy availibility f[r] ... See full document
156
Operation of Nuclear Power Stations 1993 1994
... Situation end of year : Installed capacity Maximum output capacity of which : Gas cooled reactors Advanced gas cooled reactors Light water reactors Fast reactors Others PERFORMANCES * Me[r] ... See full document
148
Operation of Nuclear Power Stations 1994 1995
... Situation end of year : Installed capacity Maximum output capacity of which : Gas cooled reactors Advanced gas cooled reactors Light water reactors Fast reactors Others PERFORMANCES * Me[r] ... See full document
148
Electrical energy monthly bulletin 5-1983
... of which : Gas cooled reactors Advanced gae cooled reactors Light water reactors Fast reactors Others Share of nuclear in : - total primary energy production - total electricity producti[r] ... See full document
16
Research and Technology Bulletin No 44, 24 February 1970
... nuclear prograrnmes which the Community d.ecid.ed to create last June for the following sectors: fast reactors, high-ternperature reactors, hcavy water reactors, highflux reactors, pJ-ut[r] ... See full document
5
Code development for integrity assessment with respect to new German safety standard
... of leak and break probabilities as well as to calculate leak rates for leak-before- break ...factors, leak areas and leak rates are ...the break preclusion ... See full document
10
Application of the Leak Before Break Concept to CANDU Feeder Piping with Service Induced Cracking
... that leak detection systems installed at the CANDU plants are more sensitive compared to those at other types of nuclear plants as a result of the costs associated with upgrading of heavy water and the presence of ... See full document
7
Application of Leak Before Break Assessment for Pressure Tube in Case of Delayed Hydride Cracking
... The Leak-Before-Break (LBB) concept is associated with the nuclear power plant design principles as regards pipe failures and their safety ...this leak during definite time can be detected by ... See full document
10
Recent Leak-Before-Break Work Associated with R6
... S21 A semi-elliptical crack with an initiation depth of 0.2mm and an initiation half-length of 1mm and a factor of 8 on the crack length.. Effects of tearing included.[r] ... See full document
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