Development methodology on determination of instant release fractions for generic safety assessment for direct disposal of spent nuclear fuel

PEACER (Proliferation-resistant, Environmental-friendly, Accident-tolerant, Continuable-energy and Economical Reactor) is a conceptual liquid metal fast reactor using Pb-Bi as a coolant and feasibility study on transmutation of spent nuclear fuel into LILW (Low and Intermediate Level Waste) using PEACER is in progress. Safety assessment of repository is essential for this feasibility study with assumption that we dispose the wastes from PWRs and PEACERs with established decontamination factors. Scenario development is one of important step for carrying out reliable and comprehensive safety assessment. This study adopted scenario development methodology from H12 report (JNC, 2000) and classified assessment scenarios into base scenario, perturbation scenarios and isolation failure scenarios. Scenarios are established by classifying, screening out and selecting FEPs with concepts and conditions of disposal for feasibility study.

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An Automated SeaFAST ICP-DRC-MS Method for the Determination of 90Sr in Spent Nuclear Fuel Leachates

Molecules ◽

10.3390/molecules25061429 ◽

2020 ◽

Vol 25 (6) ◽

pp. 1429 ◽

Cited By ~ 1

Author(s):

Víctor Vicente Vilas ◽

Sylvain Millet ◽

Miguel Sandow ◽

Luis Iglesias Pérez ◽

Daniel Serrano-Purroy ◽

...

Keyword(s):

Nuclear Fuel ◽

Safety Assessment ◽

Analytical Approach ◽

Source Term ◽

Spent Nuclear Fuel ◽

Spent Fuel ◽

Chemical Purification ◽

Radiochemical Method ◽

Good Agreement

To reduce uncertainties in determining the source term and evolving condition of spent nuclear fuel is fundamental to the safety assessment. ß-emitting nuclides pose a challenging task for reliable, quantitative determination because both radiometric and mass spectrometric methodologies require prior chemical purification for the removal of interfering activity and isobars, respectively. A method for the determination of 90Sr at trace levels in nuclear spent fuel leachate samples without sophisticated and time-consuming procedures has been established. The analytical approach uses a commercially available automated pre-concentration device (SeaFAST) coupled to an ICP-DRC-MS. The method shows good performances with regard to reproducibility, precision, and LOD reducing the total time of analysis for each sample to 12.5 min. The comparison between the developed method and the classical radiochemical method shows a good agreement when taking into account the associated uncertainties.

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The SR 97 Safety Assessment of a KBS 3 Repository for Spent Nuclear Fuel – Overview, Review Comments and New Developments

MRS Proceedings ◽

10.1557/proc-713-jj4.2 ◽

2002 ◽

Vol 713 ◽

Author(s):

Allan Hedin ◽

Ulrik Kautsky ◽

Lena Morén ◽

Patrik Sellin ◽

Jan-Olof Selroos

Keyword(s):

Nuclear Fuel ◽

Safety Assessment ◽

Spent Nuclear Fuel ◽

Bentonite Clay ◽

Research Programme ◽

High Strength ◽

Functional Requirements ◽

Future Evolution ◽

Site Investigations ◽

Potential Safety

ABSTRACTIn preparation for coming site investigations for siting of a deep repository for spent nuclear fuel, the Swedish Nuclear Fuel and Waste Management Company, SKB has carried out the longterm safety assessment SR 97, requested by the Swedish Government. The repository is of the KBS-3 type, where the fuel is placed in isolating copper canisters with a high-strength cast iron insert. The canisters are surrounded by bentonite clay in individual deposition holes at a depth of 500 m in granitic bedrock. Geological data are taken from three sites in Sweden to shed light on different conditions in Swedish granitic bedrock.The future evolution of the repository system is analysed in the form of five scenarios. The first is a base scenario where the repository is postulated to be built entirely according to specifications and where present-day conditions in the surroundings, including climate, persist. The four other scenarios show the evolution if the repository contains a few initially defective canisters, in the event of climate change, in the event of earthquakes, and in the event of future inadvertent human intrusion.The principal conclusion of the assessment is that the prospects of building a safe deep repository for spent nuclear fuel in Swedish granitic bedrock are very good. The results of the assessment also serve as a basis for formulating requirements and preferences regarding the bedrock in site investigations, for designing a programme for site investigations, for formulating functional requirements on the repository's barriers, and for prioritisation of research.SR 97 has been reviewed both by an international group of OECD/NEA experts and by Swedish authorities. The NEA reviewers concluded that “SR 97 provides a sensible illustration of the potential safety of the KBS-3 concept”, and no issues were identified that need to be resolved prior to proceeding to the investigation of potential sites. The authorities' conclusions were in principal consistent with those of the NEA.Uncertainties and lack of knowledge in different areas identified in SR 97 have strongly influenced the contents and structure of SKBs most recent research programme, RD&DProgramme 2001.Since SR 97, the methodology for probabilistic consequence analyses have been further developed. Analytic approximations to the numerical transport models used in SR 97 have been developed. The new models have been used to extend the probabilistic calculations in SR 97.

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Thermal Ionization-Isotope Dilution Mass Spectrometry Determination of Ruthenium in Spent Nuclear Fuel

Asian Journal of Chemistry ◽

10.14233/ajchem.2013.15 ◽

2013 ◽

Vol 25 (12) ◽

pp. 7044-7046 ◽

Cited By ~ 1

Author(s):

Young-Shin Jeon ◽

Yang-Soon Park ◽

Jung-Suk Kim ◽

Sun-Ho Han ◽

Yong Joon Park

Keyword(s):

Mass Spectrometry ◽

Nuclear Fuel ◽

Isotope Dilution ◽

Spent Nuclear Fuel ◽

Isotope Dilution Mass Spectrometry ◽

Thermal Ionization

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Cloud point extractive spectrophotometric method for determination of uranium in raffinate streams during spent nuclear fuel reprocessing

Journal of Radioanalytical and Nuclear Chemistry ◽

10.1007/s10967-019-06704-5 ◽

2019 ◽

Vol 322 (2) ◽

pp. 743-750 ◽

Cited By ~ 2

Author(s):

Chandan Mukhopadhyay ◽

M. Suba ◽

D. Sivakumar ◽

K. Dhamodharan ◽

R. V. Subba Rao

Keyword(s):

Cloud Point ◽

Nuclear Fuel ◽

Spectrophotometric Method ◽

Spent Nuclear Fuel ◽

Spent Nuclear Fuel Reprocessing ◽

Nuclear Fuel Reprocessing ◽

Fuel Reprocessing

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Determination of concentrations of fission products by ICP–AES in solutions from spent nuclear fuel reprocessing

Radiochemistry ◽

10.1134/s1066362217060108 ◽

2017 ◽

Vol 59 (6) ◽

pp. 618-623 ◽

Cited By ~ 2

Author(s):

Yu. A. Naumova ◽

N. V. Sapozhnikova ◽

O. N. Egorova ◽

A. A. Lumpov

Keyword(s):

Nuclear Fuel ◽

Spent Nuclear Fuel ◽

Fission Products ◽

Spent Nuclear Fuel Reprocessing ◽

Nuclear Fuel Reprocessing ◽

Fuel Reprocessing

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Environmental Safety Aspects of the New Spent Nuclear Fuel Management and Storage System at Ignalina NPP

11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B ◽

10.1115/icem2007-7248 ◽

2007 ◽

Author(s):

P. Poskas ◽

V. Ragaisis ◽

J. E. Adomaitis

Keyword(s):

Nuclear Fuel ◽

Safety Assessment ◽

Spent Nuclear Fuel ◽

Storage System ◽

Design Solution ◽

Fuel Management ◽

Nuclear Facilities ◽

Annual Dose ◽

Management Activity ◽

Dose Constraint

In the framework of the preparation for the decommissioning of the Ignalina Nuclear Power Plant (INPP) a new Interim Spent Nuclear Fuel Storage Facility (ISFSF) will be built in the existing sanitary protection zone (SPZ) of INPP. In addition to the ISFSF, the new spent nuclear fuel management activity will include all necessary spent nuclear fuel retrieval and packaging operations at the Reactor Units, transfer of storage casks to the ISFSF, and other activities appropriate to the chosen design solution and required for the safe removal of the existing spent nuclear fuel from storage pools and insertion into the new ISFSF. The Republic of Lithuania regulations require that the average annual dose to the critical group members of population due to operation of nuclear facility shall not exceed dose constraint. If several nuclear facilities are located in the same SPZ, the same dose constraint shall envelope radiological impacts from all operating and planned nuclear facilities. The paper discusses radiological safety assessment aspects as relevant for the new nuclear activity to be implemented in the SPZ of INPP considering specificity of Lithuanian regulatory requirements. The safety assessment methodology aspects, results and conclusions as concern public exposure are outlined and discussed.

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Landscape Modeling for Dose Calculations in the Safety Assessment of a Repository for Spent Nuclear Fuel

11th International Conference on Environmental Remediation and Radioactive Waste Management, Parts A and B ◽

10.1115/icem2007-7115 ◽

2007 ◽

Cited By ~ 1

Author(s):

Tobias Lindborg ◽

Ulrik Kautsky ◽

Lars Brydsten

Keyword(s):

Nuclear Fuel ◽

Safety Assessment ◽

Spent Nuclear Fuel ◽

Landscape Model ◽

Landscape Development ◽

Surface Hydrology ◽

Site Investigations ◽

Time Period ◽

The Individual

The Swedish Nuclear Fuel and Waste Management Co., (SKB), pursues site investigations for the final repository for spent nuclear fuel at two sites in the south eastern part of Sweden, the Forsmark- and the Laxemar site (figure 1). Data from the two site investigations are used to build site descriptive models of the areas. These models describe the bedrock and surface system properties important for designing the repository, the environmental impact assessment, and the long-term safety, i.e. up to 100,000 years, in a safety assessment. In this paper we discuss the methodology, and the interim results for, the landscape model, used in the safety assessment to populate the Forsmark site in the numerical dose models. The landscape model is built upon ecosystem types, e.g. a lake or a mire, (Biosphere Objects) that are connected in the landscape via surface hydrology. Each of the objects have a unique set of properties derived from the site description. The objects are identified by flow transport modeling, giving discharge points at the surface for all possible flow paths from the hypothetical repository in the bedrock. The landscape development is followed through time by using long-term processes e.g. shoreline displacement and sedimentation. The final landscape model consists of a number of maps for each chosen time period and a table of properties that describe the individual objects which constitutes the landscape. The results show a landscape that change over time during 20,000 years. The time period used in the model equals the present interglacial and can be used as an analogue for a future interglacial. Historically, the model area was covered by sea, and then gradually changes into a coastal area and, in the future, into a terrestrial inland landscape. Different ecosystem types are present during the landscape development, e.g. sea, lakes, agricultural areas, forest and wetlands (mire). The biosphere objects may switch from one ecosystem type to another during the modeled time period, from sea to lake, and from lake to mire and finally, some objects are transformed into agricultural area due to favorable farming characteristics.

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