Relevant bibliographies by topics / Accident release

Contents

  1. Journal articles
  2. Dissertations / Theses
  3. Books
  4. Book chapters
  5. Conference papers
  6. Reports

Academic literature on the topic 'Accident release'

Author: Grafiati
Published: 3 June 2025
Last updated: 31 July 2025

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Journal articles on the topic "Accident release"

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Barkan, Christopher P. L., C. Tyler Dick, and Robert Anderson. "Railroad Derailment Factors Affecting Hazardous Materials Transportation Risk." Transportation Research Record: Journal of the Transportation Research Board 1825, no. 1 (2003): 64–74. http://dx.doi.org/10.3141/1825-09.

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U.S. freight railroad accident and hazardous materials release rates have declined substantially since 1980. Ironically, this trend has made the identification and implementation of further safety improvement options more challenging because less empirical information exists on which accident causes present the greatest risks. Consequently, more sophisticated methods are needed to identify the best options for transportation risk reduction. Of particular interest is identifying the principal causes of accidents that can result in a tank car release of hazardous materials, which can harm people
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Lee, Jaejoon. "Analysis of Vulnerability during Business and Off-business Hours in Case of Hazardous Materials Release Accidents." Journal of the Korean Society of Hazard Mitigation 22, no. 4 (2022): 19–31. http://dx.doi.org/10.9798/kosham.2022.22.4.19.

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Korea has been experiencing human and environmental damage caused by accidental release of toxic chemicals such as the Gumi hydrofluoric acid accident and the Ulsan chemical accident. As the government managers do not know when, where, and how such accidents will occur, they have been trying to reduce the level of damage by recognizing victims in advance. In this study, assuming a chlorine gas release accident occurs in facilities handling hazardous chemicals, the impact range was analyzed considering the worst-case scenario of chemical release. After analyzing social, physical, and place-depe
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Saat, Mohd Rapik, and Christopher P. L. Barkan. "Release Risk and Optimization of Railroad Tank Car Safety Design." Transportation Research Record: Journal of the Transportation Research Board 1916, no. 1 (2005): 78–87. http://dx.doi.org/10.1177/0361198105191600111.

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The performance metric for tank cars and other hazardous materials vehicles involved in accidents has generally been conditional probability of release given involvement in an accident. This metric considers the probability of a release event occurring but does not take into account the quantity of product lost in a release incident. In this paper, a new metric termed “release risk” is introduced; it is defined as the expected value of the quantity lost from a tank car given that it is in an accident. The quantity of product lost varies depending on the part of the car that is damaged in an ac
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Rossi, Esko, and Matti Ettala. "Recovery analysis in risk management of hazardous materials." Water Science and Technology 33, no. 2 (1996): 133–41. http://dx.doi.org/10.2166/wst.1996.0043.

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Recovery analysis as an adjoint activity in risk assessment is to account for situational and technical aspects of a plant's preparedness for incident response and accident management. Recovery analysis has been well established in nuclear industry in evaluation of the means to prevent accident propagation. The aim of this study was to apply recovery analysis principles in the management of accidental water pollution events due to uncontrolled releases of hazardous materials. A checklist comprising possible means to prevent accident propagation, was worked out. The checklist included correctio
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Park, Jihoon, Byung-Hoon Kim, Seung-Ryul Hwang, and Choonhwa Park. "Chemical Release Accident Caused by the Abnormal Reaction of Potassium Permanganate Mixtures during Optical Film Manufacturing: A Brief Case Review." Environments 10, no. 5 (2023): 85. http://dx.doi.org/10.3390/environments10050085.

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Small- and large-scale accidents often occur in workplaces handling hazardous chemical substances. These accidents are usually caused by leaks, explosions, fires and complex chemicals; a large proportion of these chemical accidents are caused by leaks. A chemical release accident that injured four people occurred during an optical film-manufacturing process. This report analyzes the causes of this accident and provides effective measures for accident prevention. This accident was caused by an abnormal reaction during the input of raw materials prior to their heating. Tertiary butyl alcohol (t-
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Pasculescu, Vlad Mihai, Marius Cornel Suvar, Ligia Ioana Tuhut, and Laurentiu Munteanu. "Numerical modelling of hydrogen release and dispersion." MATEC Web of Conferences 342 (2021): 01004. http://dx.doi.org/10.1051/matecconf/202134201004.

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Hydrogen is the most abundant element on earth, being a low polluting and high efficiency fuel that can be used for various applications, such as power generation, heating or transportation. As a reaction to climate change, authorities are working for determining the most promising applications for hydrogen, one of the best examples of crossborder initiative being the IPCEI (Important Project of Common European Interest) on Hydrogen, under development at EU level. Given the large interest for future uses of hydrogen, special safety measures have to be implemented for avoiding potential acciden
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Fan, Xing Hua, Yan Shi, and Xue Bing Han. "Learning from Zhenjiang Water Pollution Accident." Advanced Materials Research 726-731 (August 2013): 1879–82. http://dx.doi.org/10.4028/www.scientific.net/amr.726-731.1879.

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The accident that occurred in Zhenjiang in Feburary 2012 caused chaos in local society and international attention. It was caused by chemical leak from cargo ship but the weak communication between the government and the community played a vital role. This paper analyzes the accident scenario using the risk analysis framework, determines key factors influenced the occurrence of the basic events. By comparing study we conclude that the key factors affecting such water pollution accidents includes timely information release, perfect water supply system and strict legal system.Keywords: water pol
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Hunt, C. E. L., D. S. Cox, and F. C. Iglesias. "Fission-product release during accidents — an accident management perspective." Nuclear Engineering and Design 148, no. 2-3 (1994): 205–16. http://dx.doi.org/10.1016/0029-5493(94)90110-4.

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Tsumune, D., T. Tsubono, M. Aoyama, et al. "One-year, regional-scale simulation of <sup>137</sup>Cs radioactivity in the ocean following the Fukushima Daiichi Nuclear Power Plant accident." Biogeosciences Discussions 10, no. 4 (2013): 6259–314. http://dx.doi.org/10.5194/bgd-10-6259-2013.

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Abstract. A series of accidents at the Fukushima Dai-ichi Nuclear Power Plant following the earthquake and tsunami of 11 March 2011 resulted in the release of radioactive materials to the ocean by two major pathways, direct release from the accident site and atmospheric deposition. A 1 yr, regional-scale simulation of 137Cs activity in the ocean offshore of Fukushima was carried out, the sources of radioactivity being direct release, atmospheric deposition, and the inflow of 137Cs deposited on the ocean by atmospheric deposition outside the domain of the model. Direct releases of 131I, 134Cs,
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Brandt, J., J. H. Christensen, and L. M. Frohn. "Modelling transport and deposition of caesium and iodine from the Chernobyl accident using the DREAM model." Atmospheric Chemistry and Physics Discussions 2, no. 3 (2002): 825–74. http://dx.doi.org/10.5194/acpd-2-825-2002.

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Abstract. A tracer model, DREAM (the Danish Rimpuff and Eulerian Accidental release Model), has been developed for modelling transport, dispersion and deposition (wet and dry) of radioactive material from accidental releases, as the Chernobyl accident. The model is a combination of a Lagrangian model, that includes the near source dispersion, and an Eulerian model describing the long-range transport. The performance of the transport model has previously been tested within the European Tracer Experiment, ETEX, which included transport and dispersion of an inert, non-depositing tracer from a con
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Dissertations / Theses on the topic "Accident release"

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Li, Qing 1972. "Estimate of radiation release for MIT research reactor during design basis accident." Thesis, Massachusetts Institute of Technology, 1998. http://hdl.handle.net/1721.1/9615.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1998.<br>Includes bibliographical references (leaves 84-87).<br>During a postulated design basis accident at the MIT Research Reactor (MITR), radioactive fission products may be released from melted fuel plates into the con­tainment. To comply with regulations, the whole-body dose and thyroid dose at the boundary of the exclusion area as a result of this accident are determined. The fractions of the fission products contained in the fuel that are released through the reactor coolant system (RCS) into the conta
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Ramlakan, Alastair Justin. "Modelling of fission product release from TRISO fuel during accident conditions : benchmark code comparison / Ramlakan A." Thesis, North-West University, 2011. http://hdl.handle.net/10394/7299.

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This document gives an overview of the proposed MSc study. The main goal of the study is to model the cases listed in the code benchmark study of the International Atomic Energy Agency CRP–6 fuel performance study (Verfondern & Lee, 2005). The platform that will be employed is the GETTER code (Keshaw & van der Merwe, 2006). GETTER was used at PBMR for the release calculations of metallic and some non–metallic long–lived fission products. GETTER calculates the transport of fission products from their point of fission to release from the fuel surface taking into account gas precursors and activa
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Arnesson, Jennifer. "Numerical Modeling of Radioactive Release Implemented for Loss of Coolant Accident, Evaluated using Latin Hypercube Sampling." Thesis, KTH, Reaktorfysik, 2015. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-169622.

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Plumer, Kevin E. (Kevin Edward). "Estimate of radiation release from MIT reactor with low enriched uranium (LEU) core during maximum hypothetical accident." Thesis, Massachusetts Institute of Technology, 2011. http://hdl.handle.net/1721.1/76950.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2011.<br>Cataloged from PDF version of thesis.<br>Includes bibliographical references (p. 135-137).<br>In accordance with a 1986 NRC ruling, the MIT Research Reactor (MITR) is planning on converting from the use of highly enriched uranium (HEU) to low enriched uranium (LEU) for fuel. A component of the conversion analysis includes calculating the maximum hypothetical accident (MHA) dose implications for the two types of fuel. In this work, the dose levels at the site exclusion area boundary were cal
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Corse, Brian J. "Form 2.0 fuel oxidation and release model, a computer code to predict the low volatile fission-product release and fuel volatilization from uranium dioxide fuel under severe reactor accident conditions." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1997. http://www.collectionscanada.ca/obj/s4/f2/dsk2/ftp04/mq22760.pdf.

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Caratozzolo, Vincenzo. "Development and validation of models for accident scenario following the spill of hazardous substances from pipelines." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2019.

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The releases of hazardous substance from pressurised pipelines are of particular interest due to the different scenarios that may occur following the loss of containment. These may have different causes, as accidental release, corrosion, etc. In such cases the release of flammable substances can lead to different scenarios as Fires, Explosions and Environmental pollutions. The severity of such scenarios can increase due the "Domino Effect" that will affect also other equipment or near unit operations, potentially causing a cascading event. For these reasons an accurate methodology is necessary
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Geiger, Ernesto. "Study of Fission Products (Cs, Ba, Mo, Ru) behaviour in irradiated and simulated Nuclear Fuels during Severe Accidents using X-ray Absorption Spectroscopy, SIMS and EPMA." Thesis, Université Paris-Saclay (ComUE), 2016. http://www.theses.fr/2016SACLS064/document.

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L’identification des mécanismes de relâchement des Produits de Fission (PF) hors de combustible nucléaire irradié lors d’un accident grave est primordiale pour le développement de codes capables d’estimer précisément le terme source (nature et quantité des radionucléides émis dans l’environnement). Parmi les différents PF, les Ba, Cs, Mo et le Ru sont particulièrement intéressants, car ils peuvent interagir entre eux ou avec d’autres éléments et donc affecter leur relâchement. Dans le cadre de cette thèse, deux axes de travail ont été mis en place avec l’objectif d’identifier les phases chimiq
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Elrgaiye, Ali Saad Ab. "Semi-quantitative Risk Assessment of an anaerobic digestion process." Master's thesis, Alma Mater Studiorum - Università di Bologna, 2016.

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Biogas is the most emerging industrial sector for energy production from renewable sources at National and European levels, and growing government funds favor the development of its market. From a process safety standpoint, Seveso Directive (Directive 2012/18/EU of the European Parliament and of the Council), but Biogas plants are complicated enough to require both their specific technology and an accurate risk assessment for design purposes. The number of accidents involving biogas plants has been too many to be ignored. Biogas plants are often operated wrongly, deficient in technological det
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Tavares, Richard António Martins. "Accidental release of hazardous gases: modelling and assessing risk." Doctoral thesis, Universidade de Aveiro, 2011. http://hdl.handle.net/10773/7629.

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Doutoramento em Ciências Aplicadas ao Ambiente<br>The renewed concern in assessing risks and consequences from technological hazards in industrial and urban areas continues emphasizing the development of local-scale consequence analysis (CA) modelling tools able to predict shortterm pollution episodes and exposure effects on humans and the environment in case of accident with hazardous gases (hazmat). In this context, the main objective of this thesis is the development and validation of the EFfects of Released Hazardous gAses (EFRHA) model. This modelling tool is designed to simulate t
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Ham, Marnie Elizabeth Jean. "Dispersion modelling of radioactive aerosols released during a severe nuclear reactor accident." Thesis, National Library of Canada = Bibliothèque nationale du Canada, 1997. http://www.collectionscanada.ca/obj/s4/f2/dsk2/ftp04/mq20646.pdf.

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Books on the topic "Accident release"

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S, Denning R., U.S. Nuclear Regulatory Commission. Division of Risk Analysis and Operations., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Systems Research., and Battelle Memorial Institute. Columbus Laboratories., eds. Radionuclide release calculations for selected severe accident scenarios. Division of Risk Analysis and Operations, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1986.

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Laboratory, Brookhaven National, and U.S. Nuclear Regulatory Commission. Division of Safety Issue Resolution., eds. Estimate of radionuclide release characteristics into containment under severe accident conditions: Final report. Division of Safety Issue Resolution, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1993.

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Board, United States National Transportation Safety. Hazardous materials special investigation report: Hazardous materials release, Missouri Pacific Railroad Company's North Little Rock, Arkansas railroad yard, December 31, 1984. The Board, 1985.

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United States. National Transportation Safety Board. Hazardous materials special investigation report: Hazardous materials release, Missouri Pacific Railroad Company's North Little Rock, Arkansas railroad yard, December 31, 1984. The Board, 1985.

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Miami, Fla ). International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop (5th 2011. The medical basis for radiation-accident preparedness: Medical management : proceedings of the Fifth International REAC/TS Symposium on the Medical Basis for Radiation-Accident Preparedness and the Biodosimetry Workshop, September 2011, Miami, Florida. Oak Ridge Associated Universities, 2013.

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Board, United States National Transportation Safety. Hazardous materials special investigation report: Release of oleum during wreckage-clearing following derailment of Seaboard System Railroad train Extra 8294 North, Clay, Kentucky, February 5, 1984. The Board, 1985.

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United States. National Transportation Safety Board. Hazardous materials special investigation report: Release of oleum during wreckage-clearing following derailment of Seaboard System Railroad train Extra 8294 North, Clay, Kentucky, February 5, 1984. The Board, 1985.

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1952-, Hawkes Nigel, ed. The Worst accident in the world: Chernobyl, the end of the nuclear dream. W. Heinemann, 1986.

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zdorovʹi͡a, Ukraine Ministerstvo okhorony. Стан здоров'я потерпілого населення України через 20 років пiсля Чорнобильської катастрофи. NDVP "Tekhmedekol", 2007.

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(Organization), IPHECA, ed. Health consequences of the Chernobyl accident: Results of the IPHECA pilot projects and related national programmes, summary report. World Health Organization, 1995.

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Book chapters on the topic "Accident release"

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Bera, Subrata, U. K. Paul, D. Datta, and A. J. Gaikwad. "Uncertainty in Fission Product Transient Release Under Accident Condition." In Advances in Intelligent Systems and Computing. Springer International Publishing, 2018. http://dx.doi.org/10.1007/978-3-319-74808-5_53.

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Tanaka, Satoru, and Shinichiro Kado. "Analysis of Radioactive Release from the Fukushima Daiichi Nuclear Power Station." In Reflections on the Fukushima Daiichi Nuclear Accident. Springer International Publishing, 2014. http://dx.doi.org/10.1007/978-3-319-12090-4_3.

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Ishikawa, Michio. "Release of Radioactive Materials and the Evacuation of Residents." In A Study of the Fukushima Daiichi Nuclear Accident Process. Springer Japan, 2015. http://dx.doi.org/10.1007/978-4-431-55543-8_4.

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Wilson, A., R. De Cort, and W. Crumpton. "Lessons Learned from a Major Accident Involving Uncontrolled Molten Sodium Release." In Emergency Planning Preparedness, Prevention & Response. John Wiley & Sons, Inc., 2010. http://dx.doi.org/10.1002/9780470924839.ch24.

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Nihei, Naoto. "Recovery of Food Production from Radioactive Contamination Caused by the Fukushima Nuclear Accident." In Agricultural Implications of Fukushima Nuclear Accident (IV). Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-19-9361-9_2.

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AbstractThe disastrous accident at the Tokyo Electric Power Company’s Fukushima Daiichi Nuclear Power Plant (FDNPP) in 2011 caused the release of significant amounts of radioactive waste, resulting in radiological (mainly radioactive cesium) contamination in the surrounding forests, agricultural fields, and residential areas.To ensure the safety of agricultural products grown on farmland after decontamination, Fukushima Prefecture conducted monitoring inspections on about 233,000 samples (excluding rice, grass, and other plants) in around 500 products, and is continuing to do so while narrowin
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Tatsuno, Takahiro, Hiromichi Waki, Waka Nagasawa, Naoto Nihei, Masashi Murakami, and Nobuhito Ohte. "Contribution of Cesium-Bearing Microparticles to Cesium in Soil and River Water of the Takase River Watershed and Their Effect on the Distribution Coefficient." In Agricultural Implications of Fukushima Nuclear Accident (IV). Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-19-9361-9_19.

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AbstractRadioactive cesium-bearing microparticles (CsMPs) are glassy particles containing large amounts of radioactive cesium (Cs, i.e., 134Cs and 137Cs). Because Cs in CsMPs is covered with insoluble glass, CsMPs may not release Cs into the liquid phase of river water. Previous studies have shown that CsMPs may drive overestimation of Cs transfer between the solid and liquid phases in rivers. In this study, we investigated the contribution of CsMPs to Cs concentrations in forest soil and river water in the Takase River watershed to explore the migration of CsMPs from a forest catchment and th
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Hirao, Shigekazu, Hironori Hibino, Takuya Nagae, Jun Moriizumi, and Hiromi Yamazawa. "Investigation of Uncertainty in the Release Rates of 131I and 137Cs from Fukushima Dai-ichi NPS Estimated from Environmental Data." In Radiation Monitoring and Dose Estimation of the Fukushima Nuclear Accident. Springer Japan, 2013. http://dx.doi.org/10.1007/978-4-431-54583-5_14.

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Zhang, Xueyan, Yixuan Zhang, Ye Yang, Chengcheng Deng, and Jun Yang. "Uncertainty Analysis and Sensitivity Evaluation of a Main Steam Line Break Accident on an Advanced PWR." In Springer Proceedings in Physics. Springer Nature Singapore, 2023. http://dx.doi.org/10.1007/978-981-99-1023-6_30.

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AbstractA RELAP5 input model was established for a scaled-up facility simulating China's Advanced Passive Water Reactor with passive safety features. The simulation was performed to reproduce a Main Steam Line Break (MSLB) scenario at steam line connected to one Steam Generator. The figure of merit selected in this accident scenario includes the maximum containment pressure, mass and energy release to containment. Driving factors of this response function include Passive Residue Heat Removal material thermal conductivity, Pressurizer temperature, and broken steam line temperature.To achieve an
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Hsia, Chen-Yuan, and Jyh-Der Lin. "Severe Accident Progression and Release Categories Analysis in Application to EPZ Evaluation for a BWR-4 NPP." In Proceedings of The 20th Pacific Basin Nuclear Conference. Springer Singapore, 2017. http://dx.doi.org/10.1007/978-981-10-2311-8_53.

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Boetti, Marco, Silvia Trini Castelli, and Enrico Ferrero. "Reviving MILORD Long-Range Model for Simulating the Dispersion of the Release during Fukushima Nuclear Power Plant Accident." In Air Pollution Modeling and its Application XXV. Springer International Publishing, 2017. http://dx.doi.org/10.1007/978-3-319-57645-9_61.

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Conference papers on the topic "Accident release"

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Ahn, Kwang-Il, and Jae-Uk Shin. "Assessment of Radiological Source Term Releases for Potential Severe Accident Scenarios in a PWR SFP." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81633.

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The primary purpose of this study is to assess the release of source terms into the environment for representative spent fuel pool (SFP) severe accident scenarios in a reference pressurized water reactor (PWR). For this, two typical accident scenarios (loss-of-cooling and loss-of-pool-inventory accidents) and two different reactor operating modes (normal and refueling modes) are considered in the analysis. The secondary purpose of this study is to assess the impact of an emergency makeup water injection strategy, which is one of representative SFP severe accident mitigation (SAM) strategies be
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Ono, Takuya, Koji Watanabe, Shinsuke Tashiro, Yuki Amano, and Hitoshi Abe. "HEPA Filter Clogging and Volatile Material Release Under Solvent Fire Accident in Fuel Reprocessing Facility." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-67626.

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The new licensing standards were further improved by taking into account of lessons learned from the Fukushima-Daiichi nuclear accident, and countermeasures against severe accidents were newly required as regulatory items, where severe accidents were defined as serious accidents that occur under conditions exceeding design bases. Organic solvent fire in cell was defined as one of the severe accidents in nuclear fuel reprocessing facilities, which should be investigated, in order to establish methods for evaluating effectiveness of the countermeasures. One of the combustibles in the fire accide
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Kim, Taeseok, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, and Sung Joong Kim. "Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82161.

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During a hypothesized severe accident, a containment building is designed to act as a final barrier to prevent release of fission products to the environment in Nuclear Power Plants (NPPs). However, in a bypass scenario of Steam Generator Tube Rupture (SGTR), radioactive nuclides are released to environment even if the containment is not ruptured. The radioactive nuclides are transported from primary to secondary systems through a broken steam generator tube during SGTR accident. Accordingly, the radioactive nuclides of the secondary system can be released to the environment through Main Steam
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Mintz, Todd S., George Adams, Marius Necsoiu, James Mancillas, Chris Bajwa, and Earl Easton. "Historical Rail Accident Analyses Identifying Accident Parameters That Could Impact Transportation of Spent Nuclear Fuel." In ASME 2010 Pressure Vessels and Piping Division/K-PVP Conference. ASMEDC, 2010. http://dx.doi.org/10.1115/pvp2010-25445.

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As the regulatory authority for transportation of spent nuclear fuel (SNF) in the United States, the Nuclear Regulatory Commission (NRC) requires that SNF transportation packages be designed to endure a fully engulfing fire with an average temperature of 800 °C (1,475 °F) for 30 minutes, as prescribed in Title 10 of the Code of Federal Regulations (CFR) Part 71. The work described in this paper was performed to support NRC in determining the types of accident parameters that could produce a severe fire with the potential to fully engulf a SNF transportation package. This paper describes the pr
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Bian, Zheyong, and Xiang Liu. "A Literature Review on Rail Transport of Hazmat Release Risk Analysis." In 2020 Joint Rail Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/jrc2020-8098.

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Abstract Rail plays an important role in hazmat transportation, transporting over two million carloads of hazardous materials (hazmat) in the United States annually. Compared with a truck trailer carrying a single hazmat car, a train has much more severe consequence of hazmat release due to carrying multiple connected hazmat cars (e.g., 50 to 120 flammable liquid cars). It is of high priority for the government and railroad companies to enhance the railroad hazmat transportation safety since the train accidents can cause severe railroad hazmat release incidents. Based on the data provided by F
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Choi, Wonjun, Taeseok Kim, Joongoo Jeon, Nam Kyung Kim, and Sung Joong Kim. "Sensitivity Analysis of RCS Depressurization Strategy Under a Postulated SGTR Accident in OPR1000." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-82074.

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Steam generator tube rupture (SGTR) accident is one of important accident that has high probability of resulting in severe accidents. As a bypass scenario, fission product can be directly released to the environment during the SGTR accident. Thus, the severe accident by SGTR should be carefully managed by severe accident management guidance (SAMG). In Korea, SAMG for optimized power reactor 1000 (OPR1000) has been developed in 1999 and used to mitigate the severe accident of OPR1000 with seven mitigation strategies. Among the mitigation strategies, ‘Depressurization of reactor coolant system (
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Tortorikov, M. "RADIATION CONSEQUENCES OF AN ACCIDENT AT A NPP." In РАДИАЦИОННАТА БЕЗОПАСНОСТ В СЪВРЕМЕННИЯ СВЯТ. Crossref, 2025. https://doi.org/10.34660/inf.2025.12.97.087.

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The risk to the population following a radiation accident may be increased by direct radiation from an open source or by the release and spread of radioactive substances into the environment. An accidental release of radioactive substances may occur over a very short period of time and may last for several days or even weeks depending on the development of the accident. The term "emergency protective measures" is used to describe immediate actions or protective measures that must be taken quickly to be effective. After an incident or radiation accident occurs, time is needed to predict and ass
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Sun, Shutang, Guoqiang Li, Hongchao Sun, and Jiangang Zhang. "A Study on UF6 Transportation Accident Scenarios and Diffusion Model." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66058.

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This paper discussed UF6 leak scenarios in transportation accidents, it’s different from UF6 release accident occur in nuclear fuel cycle facilities. On transport condition, physical changes and direct chemical reaction with vapor will happen after UF6 release, and then diffusion. Combined with physical properties, chemical properties and straight-line Gaussian plume models, this paper established a new diffusion model for UF6. Based on the data of three UF6 release experiments carried by the French Bordeaux National Experimental Base and calculation data of HGSYSTEM/UF6 model, the new model w
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Liu, Leilei, Weidong Liu, and Zhao Wang. "Application of Probabilistic Safety Assessment in the Risk Analysis and Management of Interface Systems LOCA in a Nuclear Power Plant." In 2022 29th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2022. http://dx.doi.org/10.1115/icone29-92253.

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Abstract Interfacing systems LOCA is a kind of special loss of coolant accident in nuclear power plants, which has an important impact on the nuclear power plants safety. Because the break of this kind of accident is located outside the containment, the interfacing systems LOCA will cause a large amount of radioactivity to be directly released from the core to the atmospheric environment without the detention of the containment, so which is an important contribution to the large early release of nuclear power plants. The Probabilistic safety assessment have been applied to a nuclear power plan
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Richmond, Mary C., Ping K. Wan, Brady P. Dague, and Kyra W. Davis. "Selection of Chemical Hazard Prediction Models for Plant Safety and Control Room Habitability Evaluations." In 2013 21st International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2013. http://dx.doi.org/10.1115/icone21-16392.

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Assuring the protection of people and the environment from unnecessary exposure to radiation is of great concern to nuclear electric power generators and regulators. In order to secure and maintain a license for operation of a nuclear power plant in the United States, the applicant is required to assess postulated scenarios to determine if an accidental chemical release either onsite or offsite will result in a design-basis event. When determining design-basis events, accident categories such as fire, explosion and/or toxic vapor cloud formation are considered. Evaluations must consider whethe
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Reports on the topic "Accident release"

1

J. Schulz. Commercial SNF Accident Release Fractions. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/850429.

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S.O. Bader. COMMERCIAL SNF ACCIDENT RELEASE FRACTIONS. Office of Scientific and Technical Information (OSTI), 1999. http://dx.doi.org/10.2172/862248.

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Denning, R. S., M. T. Leonard, P. Cybulskis, et al. Radionuclide release calculations for selected severe accident scenarios. Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6604655.

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Wagner, Kenneth. Bounding Radionuclide Release Estimates for a Hypothetical Power Reactor Accident. Office of Scientific and Technical Information (OSTI), 2022. http://dx.doi.org/10.2172/1864114.

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Bolin, J., and T. Dunn. Comparison of US/FRG accident condition fuel failure and release models. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/453988.

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Kurt G. Vedros. Fukushima Daiichi Accident Study Information Portal Quality Assurance Review: Pre-Public Release. Office of Scientific and Technical Information (OSTI), 2012. http://dx.doi.org/10.2172/1042377.

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Nourbakhsh, H. P. Estimate of radionuclide release characteristics into containment under severe accident conditions. Final report. Office of Scientific and Technical Information (OSTI), 1993. http://dx.doi.org/10.2172/10107862.

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Nourbakhsh, H. P., M. Khatib-Rahbar, and R. E. Davis. Fission product release characteristics into containment under design basis and severe accident conditions. Office of Scientific and Technical Information (OSTI), 1988. http://dx.doi.org/10.2172/6956680.

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Longhurst, G. R., R. A. Anderl, and R. J. Pawelko. Tritium loading in ITER plasma-facing surfaces and its release under accident conditions. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/282835.

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Alpert, Daniel, David Chanin, and Lynn Ritchie. Relative importance of individual elements to reactor accident consequences assuming equal release fractions. Office of Scientific and Technical Information (OSTI), 1986. http://dx.doi.org/10.2172/5854735.

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