Radionuclide transport in a long‐term operation supercritical CO 2 ‐cooled direct‐cycle small nuclear reactor

2020 ◽  
Vol 44 (5) ◽  
pp. 3905-3921
Author(s):  
Seongmin Son ◽  
Jinsu Kwon ◽  
Bong‐Seong Oh ◽  
Seong Kuk Cho ◽  
Jeong Ik Lee
Keyword(s):  
Nuclear Reactor ◽  
Radionuclide Transport ◽  
Term Operation ◽  
Direct Cycle

Helium Effects on 316L Austenitic Stainless Steel Fracture Mechanism

2016 ◽  
Vol 713 ◽  
pp. 228-231 ◽  
Author(s):  
I. Villacampa ◽  
Jia Chao Chen ◽  
Philippe Spätig ◽  
Hans Peter Seifert ◽  
F. Duval
Keyword(s):  
Fracture Mechanism ◽  
Nuclear Reactor ◽  
Pressurized Water ◽  
Term Operation ◽  
316L Austenitic Stainless Steel ◽  
Radiation Induced ◽  
Water Reactors ◽  
High Doses ◽  
Reactor Internals

The most common fracture mechanism of nuclear reactor internals is irradiation-assisted stress corrosion cracking (IASCC). Its susceptibility at relatively low dose is dominated by conventional mechanisms such as radiation-induced segregation and radiation hardening. However, the aging of the nuclear fleet combined with the increase of their life-span reveals other mechanisms that could play an important role on IASCC susceptibility. A large amount of helium (He) can be accumulated in reactor internal components of pressurized water reactors (PWR) after long term operation. This occurrence could significantly increase (or even dominate) the IASCC susceptibility at high doses. He has been homogeneously implanted in an especially designed miniaturized specimen at 300°C up to 1000 appm. Slow strain rate tests (SSRT) results in high temperature air and in simulated PWR conditions indicate that homogenized, as-implanted He does not have a significant effect on IASCC up to 1000 appm under these test conditions.

scholarly journals Prediction of prestressing losses for long term operation of nuclear reactor buildings

2011 ◽  
Vol 12 ◽  
pp. 04002 ◽  
Author(s):  
I. Cornish-Bowden ◽  
G. Thillard ◽  
B. Capra
Keyword(s):  
Nuclear Reactor ◽  
Term Operation

Utilization of Plutonium and Higher Actinides in the HTGR as Possibility to Maintain Long-Term Operation on One Fuel Loading

2002 ◽  
Author(s):  
Galina V. Tsvetkova ◽  
Kenneth L. Peddicord
Keyword(s):  
Nuclear Reactor ◽  
Fuel Composition ◽  
Inherent Safety ◽  
Fuel Loading ◽  
Pebble Bed Reactor ◽  
Term Operation ◽  
New Ideas ◽  
Physical Features ◽  
High Temperature Gas

Promising existing nuclear reactor concepts together with new ideas are being discussed worldwide. Many new studies are underway in order to identify prototypes that will be analyzed and developed further as systems for Generation IV. The focus is on designs demonstrating full inherent safety, competitive economics and proliferation resistance. The work discussed here is centered on a modularized small-size High Temperature Gas-cooled Reactor (HTGR) concept. This paper discusses the possibility of maintaining long-term operation on one fuel loading through utilization of plutonium and higher actinides in the small-size pebble-bed reactor (PBR). Acknowledging the well-known flexibility of the PBR design with respect to fuel composition, the principal limitations of the long-term burning of plutonium and higher actinides are considered. The technological challenges and further research are outlined. The results allow the identification of physical features of the PBR that significantly influence flexibility of the design and its applications.

Advanced Structural Integrity Assessment Tools for Safe Long Term Operation (ATLAS+)

2018 ◽  
Author(s):  
Sebastian Lindqvist ◽  
Kim Wallin ◽  
Dominique Moinereau ◽  
Mike Smith ◽  
Stéphane Marie ◽  
...  
Keyword(s):  
Nuclear Reactor ◽  
Structural Integrity ◽  
Assessment Tools ◽  
Experimental Proof ◽  
Term Operation ◽  
Integrity Assessment ◽  
Safety Margins ◽  
Piping Systems ◽  
Reactor Pressure

The main objective and mission of the ATLAS+ project is to develop advanced structural assessment tools to address the remaining technology gaps for the safe and long term operation of nuclear reactor pressure coolant boundary systems. This is achieved by development and validation of: • innovative quantitative methodologies to transfer laboratory material properties to assess the structural integrity of large components, • enhanced treatment of weld residual stresses when subjected to long term operation, • advanced simulation tools based on fracture mechanics methods using physically based mechanistic models, • improved engineering methods to assess components under long term operation taking into account specific operational demands, • integrated probabilistic assessment methods to reveal uncertainties and justify safety margins. Additionally, the objective is to disseminate the findings of the work through special training sessions and links to the NUGENIA association. The project scope of work focuses on piping systems of the reactor coolant pressure boundary components (RCPB) excluding the reactor pressure vessel (RPV). The project is aimed on an experimental proof of concept and validates the developed methodology both at the laboratory scale and the full scale level. The ATLAS+ project contains 4 main technical work packages and one training and dissemination package. These are summarised here.

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