Development of performance assessment models for glass dissolution

MRS Advances ◽  
2016 ◽  
Vol 1 (63-64) ◽  
pp. 4239-4245
Author(s):  
T. Goto ◽  
S. Mitsui ◽  
H. Takase ◽  
S. Kurosawa ◽  
M. Inagaki ◽  
...  

ABSTRACTNUMO and JAEA have been conducting a joint research since FY2011, which is aimed to enhance the methodology of repository design and performance assessment in preliminary investigation stage for the deep geological disposal of high-level radioactive waste. As a part of this joint research, we have been developing glass dissolution models which include various processes derived from glass-overpack-bentonite buffer interaction, considering the precipitation of Fe-silicates associated with steel overpack corrosion, and Si transport through altered layer of glass. The objective of this modeling work is to show comprehensively the lifetime of the vitrified waste due to glass matrix dissolution timescales through sensitivity analysis, and to identify the feature/process that most strongly influences the lifetime, and to identify future R&D issues that would help to improve the nuclide transport analysis with confidential value and the safety case in future. The sensitivity analysis suggested that the duration of the glass dissolution might be predicted in the ranges from 3.8×103 to 1.9×105 years. Also, the results indicated that the precipitation of Fe–silicate has the strongest influence on the long-team behavior of vitrified waste.

Author(s):  
D. A. Galson ◽  
A. Khursheed

This paper presents the results of a review of the treatment of uncertainty in performance assessment (PA) and safety-case development, carried out as part of the European Commission (EC) project PAMINA (Performance Assessment Methodologies IN Application to Guide the Development of the Safety Case). Information on the treatment of uncertainties was gathered from PAMINA participants and several other organisations using a questionnaire, and via a limited wider review of the literature. The questionnaire responses obtained represent 16 disposal programmes in 13 countries, including all of the countries with advanced programmes to implement deep geological disposal, allowing the review to give wide coverage of global activity. A two-day workshop was held in Brussels in March 2007, in which PAMINA participants reviewed an initial document which summarised the questionnaire results. Work plans were formulated for the remainder of the PAMINA programme. The 16 programmes represented are at diverse phases of maturity: four are at the conceptual development or feasibility stage, seven are at the site selection or site characterisation stage, two are at the licensing stage, one is at the construction stage, one has an operational repository, and one is at the decommissioning/closure stage. There is also wide variation in the development of regulations concerning the treatment of uncertainty for deep geological disposal of radioactive waste, with several countries having no specific regulations. The review indicates that there is a high level of consensus with respect to the nature of uncertainties in PAs and how they should be classified, although this is sometimes masked by variations in terminology and differences in the way uncertainties are treated in programmes. A system of classification is set out in this review, with reference to the nature of uncertainties. The review discusses how the principal classes of uncertainty are treated in PAs and safety cases. While nearly all programmes treat parameter and scenario uncertainties, some do not treat conceptual model uncertainties explicitly. Respondents expressed familiarity with sensitivity-analysis techniques, and clearly understand the difference between these and uncertainty analysis. It is less clear how widespread the use of sensitivity analysis is, especially formal mathematical schemes. Almost no organisations identified uncertainties that may challenge programmes, suggesting a high level of confidence in their ability to site and design deep geological disposal facilities so as to manage uncertainties effectively. However, respondents variously identified the engineered barrier system, the geosphere, the biosphere, and future human intrusion as key sources of uncertainty that require further investigation. Responses on the issue of communicating uncertainties were patchy: some respondents professed to have little experience in this area, whereas others chose not to answer the question. Some restricted themselves to discussing communication with regulators. Only a few programmes have gone as far as commissioning research into different approaches to communicating uncertainty to a variety of stakeholders.


1994 ◽  
Vol 353 ◽  
Author(s):  
J. E. Sinclair ◽  
P.J. Agg

AbstractUK Nirex Ltd is planning the deep geological disposal of intermediate- and low-level radioactive wastes. A site close to Sellafield in Cumbria in the north-west of England has been selected for evaluation, and an extensive programme of site characterization is underway. In support of this programme of characterization, and in preparation for presentation of a post-closure radiological safety case, performance assessment using mathematical modelling has been carried out by the Disposal Safety Assessment Team at AEA Technology, on behalf of UK Nirex Ltd. This paper describes recent developments of the assessment models relating to the groundwater pathway for return of radionuclides to the environment.


2020 ◽  
Vol 8 (4) ◽  
pp. 436-444
Author(s):  
T.N. Kabanova ◽  
◽  
N.E. Lysenko ◽  

The relevance of the study is due to the growing need of the state and society to improve the efficiency of the Investigative Committee of Russia. Improving the effectiveness of investigative activities is impossible without taking into account the personal characteristics of the investigator. It is important to study personal and professional resources of employees that help improve productivity and performance. More and more women choose professions that were traditionally considered male. Of scientific interest is the study of the personal characteristics of employees of the preliminary investigation units of the Ministry of Internal Affairs of Russia, where women work along with men. In this regard, the purpose of the study is to identify personal characteristics of male and female employees of investigative bodies. The article presents the research of male and female personality characteristics in the group of law enforcement authority's employees. The sample consisted of 23 officers aged 22 to 43 years (11 men, mean age was 29.18±4.05 years, 12 women, mean age 29.42±4.62 years).The average period of service in law enforcement authorities was 4.7±4.1 years. A fivefactor personality questionnaire was used in the study. It was revealed that male employees of the law enforcement authorities are characterized by a high level of self-control, a tendency to dominate, combined with perseverance and prudence. Female officers are prone to emotional stress, they also persistent, curios and tend to dominate. In addition, the influence of age and length of service on the personality characteristics of the officers, both male and female, was discovered.


Author(s):  
Joosep Pata ◽  
Alan H. Tkaczyk

It is necessary to consider the complexities of both natural and engineered components of a nuclear waste repository since fission products and minor actinides remain harmful to the environment for tens of thousands of years. In safety and performance assessments often used in decision-making about repository designs, the effect of uncertain initial guesses on the models’ output must be understood. As the necessary safe times and hence the simulated times are often in the order of magnitude of hundreds of thousands of years, uncertain initial values become increasingly important. To minimize the danger from high-level radioactive waste and to make informed decisions over designs, sensitivity analysis of the models used should be performed. The Simplified Total System Performance Assessment (STSPA) model developed by Golder Associates Inc., Booz-Allen Hamilton, Stone and Webster and the University of Nevada Reno and used in the Yucca Mountain nuclear waste repository performance assessment is analyzed for sensitivity by varying the activities of technetium-99 and iodine-129 by several orders of magnitude. The resultant dose to a maximally-exposed individual over time periods of 100,000 and 1,000,000 years is compared to the relevant regulatory limits. Incorrect estimates can be seen to have large effects on the behavior of the model while the method used allows conclusions to be drawn about the robustness of the model.


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