bluuebunny/crossref_metadata_2025_split huggingface dataset:
Strategy, main stages and progress of the Ignalina Nuclear Power Plant decommissioning
Authors: Poskas P. , Simonis V. , Smaizys A. , Sirvydas A. , Ragaisis V. , Kilda R. , Zujus R. 
Published: December 2013

Abstract
Unit 1 and Unit 2 reactors of the Ignalina Nuclear Power Plant were shutdown in December 31, 2004 and December 31, 2009, respectively. Preliminary and Final Decommissioning Plans for the Ignalina Nuclear Power Plant Units 1 and 2 were prepared, the latter of which was approved by Ministry of Economy in 2005. The main points of Final Decommissioning Plan and the main Decommissioning Projects for the Ignalina Nuclear Power Plant are summarized in this paper. Particular attention is drawn to the spent nuclear fuel and radioactive waste management projects. Preliminary analysis showed that the main mass of equipment to be dismantled is concentrated in reactor buildings (∼39%) and turbine halls (∼37%) and consists from metals of different types (∼83%). From radiological point of view, a major part (∼61%) of contaminated equipment can be classified as very low level radioactive waste.
Environmental safety aspects of the new solid radioactive waste management and storage facility at the Ignalina Nuclear Power Plant
Authors: Ragaisis V. , Poskas P. , Simonis V. , Adomaitis J. E. 
Published: December 2013

Abstract
New solid radioactive waste management and interim storage facilities will be constructed for the Ignalina Nuclear Power Plant to support ongoing decommissioning activities, including removal and treatment of operational waste from the existing storage buildings. The paper presents approach and methods that have been used to assess radiological impacts to the general public potentially arising under normal operation and accident conditions and to demonstrate compliance with regulations in force. The assessment of impacts from normal operation includes evaluation of exposure arising from release of airborne radioactive material and from facilities and packages containing radioactive material. In addition, radiological impacts from other nearby operating and planned nuclear facilities are taken into consideration. The assessment of impacts under accident conditions includes evaluation of exposure arising from the selected design and beyond design basis accidents.
Externally organized exercises for nuclear emergency response – knowlegde gained from twenty years of practical work as a technical expert adviser for radiation protection
Authors: Löffler C. , Schumacher P. 
Published: December 2013

Abstract
At the end of the eighties the TÜV NORD established an expert consultation service for radiation protection in case of nuclear accidents. Since that time, educated and regularly trained surveyors also take part as expert advisors in out of plant emergency exercises for radiation protection in the federal countries Schleswig-Holstein, Hamburg and Mecklenburg-Western Pomerania. Their responsibility is to assist and to advise the emergency response commander regarding both the predicted and the current radiological situation. Furthermore, the technical expert adviser for radiation protection communicates with other expert advisers (agent of the operator, medical staff, and meteorologists) as well as with measuring and emergency services. The experience gained during emergency exercises is summarized and documented. In the course of the past twenty years the implementation of central structures, the software systems for determination of the radiological impact and the change of communication systems have especially proved to be successful. For the future it can be assumed that exercises covering several days will be performed more often, so that not only the accident process is simulated correctly but also the conditions for the personnel of each disaster prevention unit can be simulated more realistically.
Principles of off-site nuclear emergency exercises
Authors: Miska H. 
Published: December 2013

Abstract
Due to high safety standards at nuclear power plants, no experience exits with nuclear emergencies in Western Europe. Thus, emergency exercises are the only possibility to assure effective protective measures should the very unlikely severe accident occur. The main objectives of exercises are generally the check of response plans for suitability, the test of the equipment's applicability and training of personnel for the unusual task to manage a nuclear emergency. After an introduction into the different types of exercises, this contribution focuses on off-site nuclear emergency exercises, explaining frame conditions to ensure good practice and, finally, reports some experience from exercises.
Switzerland: a culture of preparedness
Authors: Storch D. , Kenzelmann M. 
Published: December 2013

Abstract
The National NBC Protection and Coordination Office supports the activities of all members of the National NBC protection network. These include the development and implementation of operational principles, as well as training and pro-tection concepts on behalf of the head of the Steering Committee on Radioactivity (LAR) and the Federal Office for Civil Protection (FOCP), the chair of the Federal Commission for NBC Protection (ComNBC) and the chair of the Cantonal NBC Coordination Platform (KPABC). Besides exercises at the political-strategic level (civilian and military), operational training exercises are held on a regular basis.
Systematic preparation, execution and evaluation of emergency exercises at the Beznau nuclear power plant
Authors: Tenschert J. 
Published: December 2013

Abstract
Based on federal acts and a specific guideline of the nuclear authority ENSI, strict requirements are imposed on emergency exercises at Swiss NPPs. The Beznau NPP has conducted emergency exercises for more than 30 years. Systematic exercise planning assures that all emergency cases defined in the plant-specific emergency plan are considered in the exercise scenarios. Technically oriented scenarios cover all groups of initiating events and all safety levels of the defense in depth principle. The exercise results are an important input for optimization measures in the areas of emergency organization, documentation and infrastructure. Due to the goal-oriented enforcement of laws and guidelines by the nuclear authority ENSI, emergency exercises serve as a motor of further optimization of emergency preparedness.
Development of program DETSIM to simulate detector's full energy peak efficiency
Authors: Thanh T. T. , Tao C. V. , Au B. H. , Chuong H. D. 
Published: December 2013

Abstract
In this paper, the new software named DETector SIMulation (DETSIM) was developed from PENELOPE code system method to simulate gamma spectra and calculating full energy peak efficiency (FEPE). The new software is using graphic user interfaces for easy-to-use purpose. As a first application post test calculations has been performed for an experiment of a mixed source (241Am, 109Cd, 57Co, 139Ce, 51Cr, 113Sn, 85Sr, 137Cs, 60Co and 88Y) located at two positions away from detector window and energy ranges between 60 keV and 2000 keV. The results showed a general agreement between the simulated efficiencies and the experimental data. The simulation results are typically 7% higher than the experimental data in the low energy range. This means that our simulation program is good enough for later studies on our HPGe spectrometer.
Exercises of first responder organisations in Austria
Authors: Schönhacker S. 
Published: December 2013

Abstract
Although there is no nuclear industry in Austria, there are still many possible scenarios which require proper preparation through exercises. The legislative basis for the interventions of the police are the radiation protection law and the upon based interventions regulation, furthermore the penal law and the law on the transport of dangerous goods. The fire brigade has federal fire fighting laws and internal regulations as a regulatory basis. Exercises of first responder organisations take place once a year at least; the scenarios reflect the actions intended by the regulations. Aeroradiometry is a special technique conducted by the police, while the fire brigade may bring heavy equipment to use. Further improvement of the cooperation of different first responder organisations is a major goal of combined exercises.
Best estimate plus uncertainty analysis of LBLOCA for Indian PHWR
Authors: Srivastava A. , Trivedi A. K. , Lele H. G. , Munshi P. , Vaze K. K. 
Published: December 2013

Abstract
Deterministic safety analysis is an important tool for confirming the adequacy of provisions within the defense-in-depth concept for the safety of nuclear power plants. One of the important design basis events is considered to be a complete double-ended guillotine rupture i.e. Loss of Coolant Accident (LOCA) of largest and coldest pipe in the primary coolant circuit. The present work deals with this scenario for an Indian PHWR. It highlights the identification of critical break size leading to the maximum clad temperature using the best estimate code RELAP5. Further, important parameters affecting the clad temperature are described along with results of initial sensitivity studies to select dominant uncertain parameters. For the uncertainty propagation, Latin Hypercube Sampling (LHS) is used instead of simple random sampling for Monte-Carlo simulation. The inherent characteristic of LHS is to reduce the required runs for Monte-Carlo simulation to manageable order for the current computing capability. The 95th percentile value of peak cladding temperature (PCT) is obtained by the method and compared with acceptance criteria.
Dosimetric aspects of 103Pd radioactive stent source
Authors: Sadeghi M. , Kiavar O. 
Published: December 2013

Abstract
This study aims to determine AAPM TG-60 dosimetric quantities in regions surrounding the 103Pd stent wall by MCNP5 Monte Carlo code. The Palmaz-Schatz stent was modeled by a hollow cylinder of 17.89mm length (2mm diameter) with net surface very similar to real stent. The Dose deposited per photon (Gy), relative dose, Anisotropy function, F(r,θ), and radial dose function, gL(r), were described at AAPM TG-60 protocol were generated from these values and listed in tabular format. For benchmarking, the relative dose values were verified with TG-43 and EGS4 code results at identical conditions, relative to the radial distances from surface of the stent. There were noticeable results. These physical dosimetric parameters can be used in future treatment planning systems for IVBT.
Radiological significance of coal, slag and fly ash samples from the Eastern Black Sea region
Authors: Damla N. , Cevik U. , Kara A. 
Published: December 2013

Abstract
This work presents a study of natural radioactivity levels in coal and its combustion residues (fly ash and slag) used in the houses in Black Sea Region, Turkey. Coal, fly ash and slag samples were provided from different locations of the region and analyzed by gamma spectroscopy using a high-purity germanium detector (HPGe). Also, chemical analyses of these samples were carried out using energy dispersive x-ray fluorescence spectrometer. The mean 226Ra activity concentrations in coal, slag and fly ash were measured as 83, 99 and 38Bqkg–1, respectively. The mean 232Th activity concentrations in coal, slag and fly ash were measured as 108, 113 and 50Bqkg–1, respectively. The mean 40K activity concentrations in coal, slag and fly ash were found to be 366, 381 and 204Bqkg–1, respectively. The potential radiological hazards associated to these materials were evaluated by calculating the radium equivalent activity (Raeq), the air absorbed gamma dose rate (D), the annual effective dose rate (AED), the external hazard index (Hex) and internal hazard index (Hin) and compared with the internationally accepted or reference values. The mean Raeq values of the coal, fly ash and slag samples were lower than the recommended maximum values 370Bqkg–1 by the Organization for Economic Cooperation and Development (OECD). The overall mean outdoor terrestrial gamma air absorbed dose rate in coal, fly ash and slag samples are 119, 129 and 62nGyh–1 and the corresponding outdoor annual effective doses are 0.60, 0.32 and 0.64mSvy–1, which is higher than the worldwide average (0.07mSvy–1), respectively. Moreover, the enrichment factors relative to the input coal are calculated for the radionuclide contents observed. Calculated enrichment factor values for 226Ra and 232Th were found 1.14 and 1.01, respectively.
Computational models to dertermine fluiddynamical transients due to condensation induced water hammer (CIWH)
Authors: Swidersky H. , Schaffrath A. , Dudlik A. 
Published: December 2013

Abstract
Condensation induced water hammer (“condensation hammer”, CIWH) represent a dangerous phenomenon in pipings, which can endanger the pipe integrity. If they cannot be excluded, they have to be taken into account for the integrity proof of components and pipe structures. Up to now, there exists no substantiated model, which sufficiently determines loads due to CIWH. Within the framework of the research alliance CIWA, a tool for estimating the potential and the amount of pressure loads will be developed based on theoretical work and supported by experimental results. This first study discusses used computational models, results of experimental observations and gives an outlook onto future techniques.
Delayed equilibrium model and validation experiments for two-phase choked flows relevant to LOCA
Authors: Bartosiewicz Y. , Seynhaeve J.-M. , Serre G. 
Published: December 2013

Abstract
This paper deals with the 1-D Delayed Equilibrium Model (DEM) for choked or critical flow rate in steady state or quasi-steady state conditions and the selection of the relevant experimental data for assessing such models. In particular, the focus is made on thermodynamic non-equilibrium conditions, which prevail in the flashing process near the critical section. In this regard, relaxation models such as the DEM developed and tested in previous studies at UCL was revisited and improved in view of their implementation in the next CATHARE code generation during the EU NURISP (NUclear Reactor Integrated Software Platform) project. A methodology to implement the DEM into is developed. Some new results of the DEM are compared against experimental data such as Super Moby-Dick experiments done in CEA and the well-known Marviken experiments performed at quasi-real scale geometry of Nuclear Plant.
Tripartite mass transfer model: development, implementation in DYVRO, verification and validation
Authors: Neuhaus T. , Schaffrath A. 
Published: December 2013

Abstract
For the realistic simulation of condensation induced water hammer (CIWH) in horizontal pipes resulting from the contact of steam at sub-cooled water, an appropriate model for the mass and energy transfer due to phase change is needed. For this purpose the tripartite mass transfer (TMT) model has been developed that is introduced in the present paper. The TMT model is based on the assumption of isentropic processes and accounts for vaporization due to flashing, condensation due to isentropic decompression (homogenous condensation) and direct contact condensation at the phase interface. The TMT model shall be considered as a frame for sub-models which may be arranged for the three above-mentioned phase change phenomena. The TMT model has been implemented in the one-dimensional two-phase pressure surge code DYVRO mod 3. A verification and validation procedure was performed based on experiments at test facilities in Oberhausen (PPP), Rossendorf (CWHTF) and Budapest (PMK-2).
Pressure surge in Wendelstein 7-X experimental stellarator facility
Authors: Kaliatka A. , Uspuras E. , Kaliatka T. 
Published: December 2013

Abstract
Fusion is the energy production technology, which could potentially solve problems with growing energy demand of population in the future. Wendelstein 7-X (W7-X) is an experimental stellarator facility currently being built in Greifswald, Germany, which shall demonstrate that in the future energy could be produced in such type of fusion reactors. Lithuanian energy institute (LEI) in the frames of European Fusion Development Agreement (EFDA) program is cooperating with Max Planck Institute for Plasma Physics (IPP, Germany) by performing safety analysis of fusion device W7-X. In this paper the consequences of potential water hammer effects were analysed only for the case, when the plasma vessel is operating in the “baking” mode. “Baking” is the mode of facility operation during which the plasma vessel structures are heated up to 150°C in order to release absorbed gases from the surfaces and to pump them out of the plasma vessel before plasma operation. For the analysis the thermal-hydraulic model of target (torus) modules cooling / heating systems in W7-X facility was developed using RELAP5/Mod3.3 code. The performed analyses showed that the pressure pulsations in pipelines of cooling / heating systems are possible only in case of very fast closure of automatic valves in torus modules inlets and check valves in torus modules outlets. The maximum dynamic loading to cooling / heating systems pipelines due to such valves activations is in the range 0.12–0.28 MPa. Such dynamic load is insignificant and integrity of pipelines remains not violated. The pressure surge in pipeline connecting torus module in case of erroneous closure of automatic valve is eliminated due to operation of check valve on pipeline in torus module outlet.
Development of multi-group spectral code TVS-M
Authors: Lazarenko A. P. , Pryanichnikov A. V. , Kalugin M. A. , Gurevich M. I. 
Published: December 2013

Abstract
This paper is dedicated to the latest version of TVS-M code – TVS-M 2007, which allows the neutron flux distribution inside fuel assemblies to be calculated without using the diffusion approximation. The new spatial calculation module PERST introduced in TVS-M code is based on the first collisions probability method and allows the scattering anisotropy to be accounted for. This paper presents some preliminary results calculated with the use of the new version of TVS-M code.
Assessment of spectral history influence on PWR and WWER core
Authors: Bilodid Y. , Ovdiienko I. , Mittag S. , Kuchin A. , Khalimonchuk V. , Ieremenko M. 
Published: December 2013

Abstract
The few-group cross section libraries, used by reactor dynamics codes, are affected by the spectral history effect – a dependence of fuel cross sections not only on burnup, but also on local spectral conditions during burnup. Neglecting this effect leads to an additional component of error in neutron-physical characteristics. Two solution approaches to this problem implemented in the reactor dynamic code DYN3D are described and compared in this paper: a cross section correction method based on239Pu concentration and separate cross sections treatment for each axial layer of reactor core. Steady-state and burnup characteristics of a PWR and a WWER-1000 cores, calculated by DYN3D with and without cross section corrections, are compared. An impact of the correction on transient calculations is studied for a control rod ejection example. Studies have shown a significant influence of spectral history on axial power and burnup distributions as well as on calculated cycle length. Two different correction methods have shown similar major effects.
The European map of indoor radon concentrations: status and questions of quality assurance
Authors: Bossew P. , Gruber V. , Tollefsen T. , De Cort M. 
Published: December 2013

Abstract
As a first part of the long-term project “European Atlas of Natural Radiation”, a European map of indoor radon concentrations is currently under development. By mid-2011, 21 countries participate in the project, yielding a more or less complete coverage of the European territory. In this article we shortly present the current status before concentrating on questions of quality assurance. Such questions inevitably emerge in a project which attempts to integrate and harmonize large amounts of data of methodically different origin; aggregating them into a common map raises by itself questions of statistical significance.
Application of the tracer gas technology to investigate convective radon transport processes between mine workings and houses
Authors: Löbner W. , Schramm C. , Regner J. , Geringswald K. , Leichsenring F. , Schmidt P. 
Published: December 2013

Abstract
In areas featuring air-filled mine workings the convective radon transport through the disturbed bedrock is a frequent cause of high radon concentrations in dwellings. The vertical transport distance of the radon propagation can be more than one hundred meters. The application of tracer gases that can be detected by gas chromatography at extreme low concentrations allows the clear detection of mine-originated radon in dwellings and provides knowledge on the complex processes of radon transport. The successful application of the method is demonstrated on the basis of investigations of the impact of former uranium mine sites on the radon situation in dwellings.
Measurement of radionuclides within the Global Atmosphere Watch Programme of WMO
Authors: Steinkopff T. , Frank G. , Salvamoser J. 
Published: December 2013

Abstract
Within the framework of the Global Atmosphere Watch (GAW) Programme of the World Meteorological Organization (WMO), the Deutscher Wetterdienst (DWD) is taking measurements of naturally occurring radionuclides at both the environmental research platform Schneefernerhaus (2650 m a.s.l.) and the summit of Germany's highest mountain Zugspitze (2962 m a.s.l). The radionuclides measured there include 7Be, 210Pb, 212Pb, 214Pb, 214Bi, and 222Rn. This paper especially presents the direct measurement of gaseous 222Rn with a limit of detection of < 0.05 Bq/m3. When combined with meteorological data, these measurements provide a valuable database for characterising air masses and a useful supplementary tool evaluating air transport models and identifying global atmospheric conditions.
Remarks on boiling water reactor stability analysis – part 2: stability monitoring
Authors: Lange C. , Hennig D. , Hurtado A. , Schuster R. , Lukas B. , Aguirre C. 
Published: December 2013

Abstract
In part 1 of this article we explained the partly relative complex solution manifold of the differential equations describing the stability behaviour of a BWR, in particular the coexistence of different types of solutions, such as the coexistence of unstable limit cycles and stable fixed points are of interest from the operational safety point of view. The part 2 is devoted to the surveillance of the stability behaviour. We summarize some stability monitoring methods and suggest to support stability tests by RAM-ROM analyses in order to reveal in advance the stability “landscape” of the BWR in a parameter region high sensitive for appearing of linear unstable states. The analysis of an especial stability test, performed at NPP Leibstadt (KKL), makes it clear that the measurement results can only be interpreted by application of bifurcation analysis.
Nuclear aspects and cyclotron production of the positron emitter 55Co
Authors: Talebi M. , Kakavand T. , Mirzaii M. 
Published: December 2013

Abstract
The radionuclide 55Co (T1/2 = 17.5 h, Eβ+ = 1.5 MeV, 76% β+ decay) is an important β+ emitting radioisotope. For production of 55Co via natFe(p, xn) 55Co reaction, an iron layer was deposited on a copper substrate by means of electro-deposition method which could be irradiated by 29.5 MeV protons at 100 μA. No-carrier-added (n.c.a.) 55Co was separated from the iron target via an anion exchange column (Dowex 1 · 8). The achieved production yield was 31.25 MBq/μAh. Also, excitation functions for the 55Co radionuclide via natFe(p, xn)55Co, 56Fe(p, 2n)55Co and 54Fe(d, n)55Co reactions were calculated by TALYS-1.4 code and TENDL-2011 database and compared with previous published data.