On the nuclear safety improvement by post-inerting small modular reactor with stainless steel cladding

2020 ◽  
Vol 149 ◽  
pp. 107775
Author(s):  
Alan Matias Avelar ◽  
Marcelo Breda Mourão ◽  
Marcos Maturana ◽  
Claudia Giovedi ◽  
Alfredo Yuuitiro Abe ◽  
...  
Author(s):  
Lei Wan ◽  
Guiyong Li ◽  
Min Rui ◽  
Yongkang Liu ◽  
Jue Yang

A floating nuclear power plant (FNPP) with small modular reactor (SMR) is a combination of a civilian nuclear infrastructure and an offshore installation, which is defined as a floating nuclear facility. The article draws the lessons from studying of the engineer combination like Floating Production Storage and Offloading (FPSO) under the regulation of several government departments. It puts forward recommendations for license application and government regulation as follows in consideration with current license application for nuclear power plant and ship survey. A FNPP shall follow the requirements of construction, fueling and operation for civil nuclear installation combined with ship survey. Application is submitted to nuclear safety regulator for construction permit, while the design drawings shall be submitted to department of ship survey which checks the drawings whether meet the requirements of ship survey, considering some nuclear safety needs. The result of ship survey shall be represented in the safety analysis reports. The construction and important devices manufacturing shall be under the supervision of nuclear installation regulators and ship survey departments. In conclusion, National Nuclear Safety Administration (NNSA) and Maritime Safety Administration of the People’s Republic of China (MSA) shall establish united supervisory system for SMR on sea in China. It is suggested that NNSA is in charge of the overall safety of a FNPP, while MSA is responsible of the ship survey. The operator shall undertake obligation of a FNPP and evaluate the ship cooperating with experienced agency. It is suggested that government departments build the mutual recognition agreement of safety review. It is better to solve the vague questions by coordination.


2019 ◽  
Vol 817 ◽  
pp. 642-649
Author(s):  
Alberto Viskovic ◽  
Libbio Antonelli ◽  
Filippo Morgante

This paper shows the efficiency of the vertical and annular post-compression for wind and seismic structural behavior improvement of slender masonry chimney. For this aim a case study approach regarding an old masonry chimney is used. The paper shows the safety analysis and the safety improvement obtained applying at the same time a vertical and an annular masonry post-compression. The vertical post-compression is obtained through the post-tensioning of twenty-four vertical stainless-steel thin bars. These bars are connected to the chimney masonry only at the basement and at the top. They are placed inside the central void and horizontally distributed along a circumference near the inside face of the masonry, but without to touch it. The annular post-compression is obtained post-tensioning forty-five annular aramidica “not twisted” cables, placed and glued (after the post-tensioning) inside horizontal mortar joints of the more external masonry brick layer.


2020 ◽  
pp. 4-13
Author(s):  
O. Zhabin ◽  
O. Pecherytsia ◽  
S. Tarakanov ◽  
I. Shevchenko

The Canadian Nuclear Safety Commission (CNSC) has recently completed the first phase of the pre-licensing vendor design review (VDR) for the SMR-160 small modular reactor (SMR) designed by Holtec International (USA). This event is an example of early involvement of the regulatory authority into review of the safety assessment for SMR design developed in compliance with standards and rules of another country. This example deserves a detailed analysis considering that the introduction of SMR technology is potentially attractive for Ukraine and there is national interest in this area. The paper presents an overview of the regulatory framework governing the pre-licensing VDR by CNSC: objective, initial conditions, main stages, technical content and general expected results of this process. According to the first phase of the review performed for the SMR-160 design, information on the main aspects addressed for each technical area and the main review findings are provided. Since the implementation of relevant advanced practices is reasonable and relevant, the paper proposes to consider the development and implementation of regulatory framework for the national nuclear regulatory authority to perform further pre-licensing reviews of designs using the latest foreign technologies.


2020 ◽  
Vol 9 (1) ◽  
pp. 99-106
Author(s):  
Kevin W. Lee

Over the course of the last several years the Canadian Nuclear Safety Commission (CNSC) has engaged with numerous vendors and potential licenses of small modular reactor (SMR) technology. This paper discusses what an SMR is and what potentially makes them different from standard nuclear power plants (NPP). Readiness activities for the potential licensing of SMRs are described as well as modifications being made to the CNSC’s existing regulatory framework to facilitate the same, without reducing safety. The role of the CNSC’s discussion paper DIS-16-04, Small Modular Reactors: Regulatory Strategy, Approaches and Challenges (DIS 16-04) and how feedback received on it helped confirm the CNSC’s modifications to be undertaken to the regulatory framework, as well as areas requiring further clarity, are highlighted. Finally, the role of the CNSC Vendor Design Review process is described as well as other readiness activities undertaken by the CNSC that are helping to ensure that the CNSC will be ready to accept and evaluate a license application for an SMR.


Author(s):  
L.E. Murr ◽  
J.S. Dunning ◽  
S. Shankar

Aluminum additions to conventional 18Cr-8Ni austenitic stainless steel compositions impart excellent resistance to high sulfur environments. However, problems are typically encountered with aluminum additions above about 1% due to embrittlement caused by aluminum in solid solution and the precipitation of NiAl. Consequently, little use has been made of aluminum alloy additions to stainless steels for use in sulfur or H2S environments in the chemical industry, energy conversion or generation, and mineral processing, for example.A research program at the Albany Research Center has concentrated on the development of a wrought alloy composition with as low a chromium content as possible, with the idea of developing a low-chromium substitute for 310 stainless steel (25Cr-20Ni) which is often used in high-sulfur environments. On the basis of workability and microstructural studies involving optical metallography on 100g button ingots soaked at 700°C and air-cooled, a low-alloy composition Fe-12Cr-5Ni-4Al (in wt %) was selected for scale up and property evaluation.


Author(s):  
J. A. Korbonski ◽  
L. E. Murr

Comparison of recovery rates in materials deformed by a unidimensional and two dimensional strains at strain rates in excess of 104 sec.−1 was performed on AISI 304 Stainless Steel. A number of unidirectionally strained foil samples were deformed by shock waves at graduated pressure levels as described by Murr and Grace. The two dimensionally strained foil samples were obtained from radially expanded cylinders by a constant shock pressure pulse and graduated strain as described by Foitz, et al.


Author(s):  
R. Gonzalez ◽  
L. Bru

The analysis of stacking fault tetrahedra (SFT) in fatigued metals (1,2) is somewhat complicated, due partly to their relatively low density, but principally to the presence of a very high density of dislocations which hides them. In order to overcome this second difficulty, we have used in this work an austenitic stainless steel that deforms in a planar mode and, as expected, examination of the substructure revealed planar arrays of dislocation dipoles rather than the cellular structures which appear both in single and polycrystals of cyclically deformed copper and silver. This more uniform distribution of dislocations allows a better identification of the SFT.The samples were fatigue deformed at the constant total strain amplitude Δε = 0.025 for 5 cycles at three temperatures: 85, 293 and 773 K. One of the samples was tensile strained with a total deformation of 3.5%.


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