Safety Assessment of Smart Instruments for the Nuclear Industry

2014 ◽  
Author(s):  
G.C. Corrao ◽  
S. Hatton ◽  
J. Lewthwaite
Keyword(s):  
Safety Assessment ◽  
Nuclear Industry

Safety Assessment Principles Applied to Small Modular Reactors

2011 ◽  
Author(s):  
Neil F. Harman ◽  
Guy S. Anderson ◽  
John N. Lillington ◽  
Russ V. Booler
Keyword(s):  
Nuclear Power ◽  
Safety Assessment ◽  
Nuclear Industry ◽  
Regulatory Regime ◽  
Design Assessment ◽  
Advantages And Disadvantages ◽  
General Terms ◽  
Small Modular Reactors ◽  
The Uk ◽  
The Impact

Much of the attention on small modular reactors (SMRs) has to date been focused on the technology or novel applications, however, this paper tries to set out some thoughts on some of the other issues, or “externalities” within which any SMR proposal must be brought to market. The Paper outlines the UK regulatory regime highlighting differences from that in the US. Regulation in the UK is based on Safety Assessment Principles rather than a prescriptive set of requirements; the amenability of such a regime to assessing novel reactor designs and applications is discussed in general terms. The Paper summarizes the licensing arrangement for nuclear facilities used by the UK nuclear regulator. It goes on to summarize the recent Generic Design Assessment (GDA) programme for new build in the UK in which Serco has been heavily involved. The Safety Assessment Principles reach further than just into the technicalities of engineering design. Two particular areas of interest are picked out: the availability of qualified and experienced personnel and the impact on plant as a result of grid and transmission system issues. With regard to the first of these, in the early days of nuclear power, the UK considered many different reactor designs including gas cooled reactors, fast reactors, heavy water reactors, high temperature reactors and later a small reactor design — the SIR (Safe Integral Reactor) — although this was never built; these are briefly described highlighting any similarities to current proposed small reactor designs and concepts and discussing any lessons that could be learned. Staff in Serco have been involved with all these developments as well as undertaking research in Generation IV concepts. To begin to address the impact on the plant from its interface with the external electricity grid system, the Paper discusses the energy market in the UK (one of the most deregulated), the state of the nuclear industry, the current political landscape as far as nuclear power is concerned, and the prospects for deploying small modular reactors in the UK. It then considers the implications of the European Union’s challenge to decarbonize electricity supply by 2050. Finally, the Paper considers other pertinent issues associated with small reactor concepts and the Safety Assessment Principles. It discusses some of the issues around inspection, given that many of the small reactor concepts are based on underground reactors. Given the smaller size of SMRs, the opportunities for association with novel non-power generating applications are greater than for conventional plant. Some differences associated with these proposals, compared to traditional nuclear power generation, are examined. The paper then also discusses the advantages and disadvantages, as far as safety is concerned, of a farm of small modular reactors compared with a single large reactor.

scholarly journals Effect of Molten Corium Behavior Uncertainty on the Severe Accident Progress

2018 ◽  
Vol 2018 ◽  
pp. 1-9 ◽  
Author(s):  
Wonjun Choi ◽  
Taeseok Kim ◽  
Joongoo Jeon ◽  
Nam Kyung Kim ◽  
Sung Joong Kim
Keyword(s):  
Safety Assessment ◽  
Sampling Method ◽  
Latin Hypercube Sampling ◽  
Nuclear Industry ◽  
Severe Accident ◽  
Data Sets ◽  
Human Reliability Analysis ◽  
Rank Regression ◽  
Drainage Rate ◽  
Uncertainty Parameters

Uncertainty of a severe accident code output needs to be handled reliably considering its use in safety regulation of nuclear industry. In particular, severe accident codes are utilized for probabilistic safety assessment (PSA), where the uncertainty of severe accident progress should be considered carefully due to its influence on human reliability analysis. Therefore, in this study, the uncertainty analysis of severe accident progress was performed using MELCOR code, and a total of 200 data sets of in-vessel uncertainty parameters were generated by Latin hypercube sampling method. The rank regression analysis was also performed to investigate the effect of uncertainty parameters on the severe accident progress. Sensitivity coefficients (SCs) in MELCOR such as molten clad drainage rate and zircaloy melt breakout temperature showed significant influence on relocation time and dryout time of lower plenum. However, the influence of uncertainty parameter diminished as the accident progressed.

scholarly journals AN INTEGRATED RISK INFORMED DECISION MAKING IN THE NUCLEAR INDUSTRY

2013 ◽  
Vol 3 (2) ◽  
pp. 22-34
Author(s):  
Mieczysław Józef Borysiewicz ◽  
Karol Kowal ◽  
Piotr Prusiński ◽  
Marcin Dąbrowski
Keyword(s):  
Decision Making ◽  
Safety Assessment ◽  
Integrated Approach ◽  
Nuclear Industry ◽  
Decision Making Process ◽  
Regulatory Body ◽  
Deterministic Approach ◽  
Nuclear Facilities ◽  
Integrated Risk ◽  
Traditional Manner

The regulatory body, established to ensure safety of nuclear facilities, is expected to make right decisions and provide appropriate regulations for the nuclear industry. The traditional manner of its activity has been based on a deterministic approach to safety analyses. However, increased maturity of Probabilistic Safety Assessment (PSA) makes it complementary to deterministic studies. The new IAEA concept, described in this article, is to apply an integrated approach by combining both deterministic and probabilistic insights with other requirements affecting the decision making process.

Point Defect Absorption and Dislocation Loop Formation at Grain Boundaries in Hvem-Irradiated Zr and Its Alloys:1. Influence of Solute Addition

1985 ◽  
Vol 43 ◽  
pp. 350-351
Author(s):  
R.A. Herring ◽  
M. Griffiths ◽  
M.H Loretto ◽  
R.E. Smallman
Keyword(s):  
Grain Boundary ◽  
Grain Boundaries ◽  
Point Defect ◽  
Reactor Core ◽  
Solute Concentration ◽  
Nuclear Industry ◽  
Dislocation Loops ◽  
Loop Formation ◽  
Component Material ◽  
Impurity Interaction

Because Zr is used in the nuclear industry to sheath fuel and as structural component material within the reactor core, it is important to understand Zr's point defect properties. In the present work point defect-impurity interaction has been assessed by measuring the influence of grain boundaries on the width of the zone denuded of dislocation loops in a series of irradiated Zr alloys. Electropolished Zr and its alloys have been irradiated using an AEI EM7 HVEM at 1 MeV, ∼675 K and ∼10-6 torr vacuum pressure. During some HVEM irradiations it has been seen that there is a difference in the loop nucleation and growth behaviour adjacent to the grain boundary as compared with the mid-grain region. The width of the region influenced by the presence of the grain boundary should be a function of the irradiation temperature, dose rate, solute concentration and crystallographic orientation.

Abstract #379 The Eversense CGM System Accuracy and Safety Assessment on the Abdomen Compared to the Upper Arm in a Home Use Setting

2019 ◽  
Vol 25 ◽  
pp. 173
Author(s):  
Magnus Löndahl ◽  
Mona Landin-Olsson ◽  
Stig Attval ◽  
Colleen Mdingi ◽  
Katherine S Tweden
Keyword(s):  
Safety Assessment ◽  
Upper Arm

Work Safety Assessment

2012 ◽  
Author(s):  
Keyword(s):  
Safety Assessment ◽  
Work Safety

Nuclear industry has a bright future

2012 ◽  
pp. 74-75
Author(s):  
Luc Oursel
Keyword(s):  
Nuclear Industry ◽  
Bright Future
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