{"title":"Mobile radiation dosimeter for monitoring of total radiation on-board of civilian aircraft.","authors":"V. Elin, Olga N. Sharts, M. Merkin","doi":"10.1504/IJNSS.2019.10020602","DOIUrl":"https://doi.org/10.1504/IJNSS.2019.10020602","url":null,"abstract":"This paper describes a novel radiation dosimeter technology 'DO-RA' and its uses in commercial flights as 'DO-RA.AVIA' semiconductor module incorporated into smartphones and other electronic devices. We discuss issues of radiation exposure during flights, including possible health risks, and provide an example of experimental data regarding radiation exposure during particular flight, taken recently during 2-hour flights within Russia and in France, which can open reader's eyes to the potential impact of ionising radiation that occurs during the air flights. The article describes 'DO-RA' radiation measurement technology features and functions, demonstrates uses of 'DO-RA.AVIA' radiation measurement module for use in-flight of commercial aircraft. The article suggests more features and uses of 'DO-RA' technology for drug-discovery in-house use, outdoor applications, surveillance and as a gadget for automobiles' gadget.","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"43 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-06-07","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"128264802","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Thermal hydraulic simulations of a PWR nuclear power plant","authors":"S. Ibrahim, Sami. I. Atia","doi":"10.1504/IJNSS.2019.10018393","DOIUrl":"https://doi.org/10.1504/IJNSS.2019.10018393","url":null,"abstract":"This research presents simulation analyses of steady state, station blackout, and loss of coolant accident thermal hydraulic conditions. The plant is a PWR type with output of about 1000 MWe. The simulations are performed by using RELAP and PCTran codes to develop a model of this PWR which could simulate its primary system, with good accuracy in cases of steady state, station blackout, and loss of coolant accidents. The modelled core temperature distribution, pressure, coolant mass flow inlet and outlet temperatures of the reactor, and other parameters proved to be in good agreement with reference data. These simulations verify the efficiency of management procedures in ensuring that the auxiliary cooling systems can cool the reactor core during accident conditions. The importance of the auxiliary system during the accident conditions is accredited. The developed RELAP and PCTran models are capable of reproducing the thermal hydraulic behaviour of the PWR.","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"56 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126873335","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Developing a consequence management assessment framework","authors":"Kenneth W. McDonald, Rob Prins","doi":"10.1504/IJNSS.2019.10020601","DOIUrl":"https://doi.org/10.1504/IJNSS.2019.10020601","url":null,"abstract":"This research developed an assessment process framework and tool to assess national consequence management capacity. The research applied a value focused thinking and the Systems Design Process (SDP) to create a framework that effectively analyses a nation's capacity to handle extreme crisis situations to include Chemical, Biological, Radiological, Nuclear and Explosive (CBRNE) events. The research conducted extensive stakeholder analysis to identify critical metrics in identifying a nation's capacity and capabilities. Weighting and scoring of the value metrics was applied to develop scoring assessments. The results provided a usable assessment model that tracks capacity progress over time. The model provides a value contribution to the development of an effective assessment tool and achieves the goal of providing a practical tool for assessment. This research takes assessing a very difficult and complex system and makes it relatively easy and simple, while providing solid evidence of capacity improvement or deterioration over time.","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"15 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"124286948","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Passive containment cooling system with hydrogen recombiner for prolonged station blackout","authors":"S. Revankar","doi":"10.1504/IJNSS.2019.10021648","DOIUrl":"https://doi.org/10.1504/IJNSS.2019.10021648","url":null,"abstract":"Beyond design basis accident scenario, where station blackout could lead to severe accident with hydrogen release, has become important after accident at Fukushima Daiichi nuclear plant. Here a passive containment cooling system (PCCS) combined with hydrogen mitigation system is suggested that will passively remove containment heat load as well as mitigate hydrogen gas generated and accumulated in the containment atmosphere during prolonged station blackout. It is proposed to make use of atmosphereic air as ultimate heat sink to reject the PCCS heat, which in turn transfers heat from the containment. In the proposed design a finned vertical tube type PCCS system submersed in pool water is considered with supply of pool water lasting three days following which airflow cools PCCS tubes for long term. The PCCS inlet flow path has a catalytic recombiner that is effective during first few days should there be any hydrogen generation and accumulation in the containment.","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"6 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"2019-05-31","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"127652398","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Use of nuclear material accounting and control for augmenting nuclear security: a logical step but challenges remain","authors":"K. L. Ramakumar","doi":"10.1504/IJNSS.2021.10032444","DOIUrl":"https://doi.org/10.1504/IJNSS.2021.10032444","url":null,"abstract":"","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"82 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"129139015","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Physical protection systems of nuclear facilities: a proposed nuclear power plant general layout and regulatory requirement","authors":"M. F. Barakat, O. A. Elhefnawy","doi":"10.1504/ijnss.2019.10021653","DOIUrl":"https://doi.org/10.1504/ijnss.2019.10021653","url":null,"abstract":"At present, great efforts in Egypt are directed towards elaborate physical protection regulations to protect nuclear and radiological facilities from any adversary actions, especially after signing the agreement between Egypt and Russia for the establishment of the first Egyptian nuclear power plant in Dabaa. The upcoming regulations will include a physical protection regulation of nuclear facilities and nuclear materials. Thus, the present work is concerned with a proposal of physical protection regulation of nuclear facilities. This proposal discusses the role of the licensee in defining threat assessment and design basis threat followed by classifying different areas in general layout of nuclear facility or nuclear power plant. Also, the requirements of an efficient physical protection system are discussed based on the four basic elements, i.e. entry control, intrusion detection, delay of intruder, and response force. This suggested regulation takes into consideration the International Atomic Energy Agency recommendations and many other countries’ regulations.","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"1 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"130517287","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"Kenya's nuclear energy dilemma","authors":"Kenneth K. Mbali, Justus J. Okonda","doi":"10.1504/ijnss.2022.10052031","DOIUrl":"https://doi.org/10.1504/ijnss.2022.10052031","url":null,"abstract":"","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"82 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"126441258","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
Moazzem Hossain, Md. Abdul Malek Soner, A. Mahmud, Md. Sayed Hossain, Tamanna Yeasmin Usha, Md. Maidul Islam, A. Zoardar, Ashraful Haque, M. M. Uddin, Nusrat Jahan
{"title":"Experiences and Challenges of Nuclear Safeguards Activities in Bangladesh","authors":"Moazzem Hossain, Md. Abdul Malek Soner, A. Mahmud, Md. Sayed Hossain, Tamanna Yeasmin Usha, Md. Maidul Islam, A. Zoardar, Ashraful Haque, M. M. Uddin, Nusrat Jahan","doi":"10.1504/ijnss.2022.10049351","DOIUrl":"https://doi.org/10.1504/ijnss.2022.10049351","url":null,"abstract":"","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"8 11","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"113979370","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}
{"title":"The effect of reactor safety containment geometry changes on thermo-hydraulic parameters at the time of the accident","authors":"M. Sadeghiazad, F. C. Rahim","doi":"10.1504/ijnss.2022.10052892","DOIUrl":"https://doi.org/10.1504/ijnss.2022.10052892","url":null,"abstract":"","PeriodicalId":113793,"journal":{"name":"International Journal of Nuclear Safety and Security","volume":"13 1","pages":"0"},"PeriodicalIF":0.0,"publicationDate":"1900-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":null,"resultStr":null,"platform":"Semanticscholar","paperid":"123036242","PeriodicalName":null,"FirstCategoryId":null,"ListUrlMain":null,"RegionNum":0,"RegionCategory":"","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":"","EPubDate":null,"PubModel":null,"JCR":null,"JCRName":null,"Score":null,"Total":0}