Academic literature on the topic 'Pressurized steam'

Kurtz, R. J. Steam generator group project: Annual report, 1985. Division of Engineering Safety, Office of Nuclear Regulatory Researach, U.S. Nuclear Regulatory Commission, 1987.

Turner, C. W. Mechanisms of magnetite deposition in pressurized boiling and non-boiling water. System Chemistry and Corrosion Branch, Chalk River Laboratories, 1994.

Zverkov, V. V. I͡A︡dernai͡a︡ paroproizvodi͡a︡shchai͡a︡ ustanovka s VVĖR-440. Ėnergoatomizdat, 1987.

Frank, L. Steam generator operating experience update for 1987-1988. Division of Engineering and Systems Technology, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1989.

Rogers, J. M. An analysis of semiscale Mod-2C S-FS-1 steam line break test using RELAP5/MOD2. U.S. Nuclear Regulatory Commission, 1992.

Stubbe, E. J. Assessment study of RELAP-5 MOD-2 cycle 36.01: Based on the Doel-2 steam generator tube rupture incident of June 1979. U.S. Nuclear Regulatory Commission, 1986.

He dian chang zheng qi dong li zhuan huan xi tong: Steam power conversion system of nuclear power plants. Yuan zi neng chu ban she, 2010.

Odar, F. Assessment of the TRAC-M codes using Flecht-Seaset reflood and steam cooling data. U.S. Nuclear Regulatory Commission, 2001.

Yidong, Zhou, and Huang Xingrong, eds. He dian chang he zheng qi gong ying xi tong: Nuclear steam supply system of nuclear power plants. Yuan zi neng chu ban she, 2010.

Lee, R. Y. Thermal-hydraulic research plan for Babcock and Wilcox plants. Division of Reactor and Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1988.

Wan Mohamad, Wan Munirah, Tahir Ahmad, and Azmirul Ashaari. "Modeling Steam Generator System of Pressurized Water Reactor Using Fuzzy Arithmetic." In Communications in Computer and Information Science. Springer Singapore, 2016. http://dx.doi.org/10.1007/978-981-10-2777-2_21.

Kado, Shigeru, Mohammad Nurunnabi, Yuya Mukainakano, et al. "Performance and Characterization of NiO-MgO Solid Solution Modified with Noble Metals in Oxidative Steam Reforming of Methane under Pressurized Conditions." In ACS Symposium Series. American Chemical Society, 2007. http://dx.doi.org/10.1021/bk-2007-0959.ch006.

Paul, Deepraj, S. Pahari, S. Hajela, and M. Singhal. "Transient Analysis of Pressurizer Steam Bleed Valves Stuck Open for 700 MWe PHWRs." In Proceedings of the 7th International Conference on Advances in Energy Research. Springer Singapore, 2020. http://dx.doi.org/10.1007/978-981-15-5955-6_90.

Muscroft, J. "2. Modern large 3000 rev/min steam turbines for pressurized water reactor power stations." In Technology of turbine plant operating with wet steam. Thomas Telford Publishing, 1989. http://dx.doi.org/10.1680/totpowws.13957.0003.

Meier, Paul F. "Nuclear." In The Changing Energy Mix. Oxford University Press, 2020. http://dx.doi.org/10.1093/oso/9780190098391.003.0005.

"Corrosion Fatigue Cracking of a Steam Generator Vessel From a Pressurized Water Reactor." In Handbook of Case Histories in Failure Analysis. ASM International, 1992. http://dx.doi.org/10.31399/asm.fach.v01.c9001051.

Bittanti, S., R. Cori, F. Pretolani, L. Rassu, and D. Roncaglioni. "IDENTIFICATION OF A PRESSURIZED WATER REACTOR STEAM GENERATOR BY STATE-SPACE MULTI-VARIABLE MODELS." In Control Science and Technology for Development. Elsevier, 1986. http://dx.doi.org/10.1016/b978-0-08-033473-8.50016-4.

POULTER, L. N. J., A. ROGERSON, D. G. DAWSON, and V. R. GREEN. "36. In-service inspection techniques for PWR steam generator feedwater and pressuriser nozzles." In Remote techniques for inspection and refurbishment of nuclear plant. Thomas Telford Publishing, 1988. http://dx.doi.org/10.1680/rtfiaronp.13889.0028.

Matal, O., J. Soukup, and J. Šírek. "TEMPERATURE CHANGES AND THERMAL STRESSES IN A STEAM GENERATOR AND PRESSURIZER PRESSURE VESSELS ARISEN DURING OPERATION OF THE WER NUCLEAR POWER PLANT." In Design & Analysis. Elsevier, 1989. http://dx.doi.org/10.1016/b978-1-4832-8430-9.50047-2.

"freezing out, adsorption and absorption. After concentrating, separation is achieved by classical methods such as gas chranatography (GC) or high pressure liquid chranatography (HPLC). Identification is based mainly on mass spectrometry, infra-red spectrometry and chrcmatographic data. 3. RESULTS The primary goal of these methods is to concentrate all volatile com­ pounds, mainly volatile organic compounds or VOCs, present. This mixture of VOCs, containing odorous ccmpcunds, next to a large majority of unodo-rous substance, then is analysed. This chemical analysis is based on the separation of these hundreds of compounds by gas chranatography, is hampe­ red by large amounts of water, which is always present in air, and which is also freezed out or adsorbed. The only way to escape more or less this difficulty is to use a rather apolar adsorbant, in casu Tenax GC or similar materials (e.g. Chranosorb 102) (5). A second limitation is the fact that no material will ever be capable of adsorbing all odorous com­ pounds completely, and permit to desorb then afterwards completely. For compounds with very low boiling point, e.g. hydrogen sulphide, strong ad-sorbants are necessary, while for odorants with high boiling point, e.g. skatol or the sesquiterpenes, thermal desorption is difficult with strong adsorbant s. So a compromise has to be accepted, or several complementa­ ry adsorbants have to be used. At this moment this compromise for concen­ trating all odorous substances is found in the adsorbant mentioned, kno­ wing that the most volatile compounds might escape partly. Many systems have been described and even carenercialised, but we use a home-built sy­ stem, which is schematically represented in figure 1 (6). On an outer side wall of the gas chromatograph (GC) an oven in which the Tenax-adsorp-tion-sampling tubes fit is constructed. Connections with pressurized he­ lium (transfer gas) is provided and their is a connection with a high tem­ perature resistant sixway valve, which replaces the normal GC-injector. During thermal desorption (position 1 in figure 1) the transfer gas, car­ rying desorbed volatiles, passes the sixway valve, a cold trap (stainless steel loop cold with liquid air) and enters the ambient air. The helium carrier gas is connected to the GC-column via the sixway valve. After the desorption stage which usually takes about 45 minutes, with a desorption oven temperature of 220°C for 30 minutes at least, the sixway valve is switched (position 2 in figure 1). At that moment transfer gas flows through the sixway valve directly into the ambient whereas the carrier gas passes the cold trap before entering the GC-column. The liquid air is removed from the cold trap and the latter is quickly heated by a high in­ tensity fload light. In this way condensed compounds are flash-evaporated and injected into the GC-system. Concentrating odorants by adsorption-desorption techniques produces a terribly complex mixture of VOCs, which is separated by gas chranato­ graphy. Fortunately this technique allows formidable separation power, but still then the result is not always sufficient far a clear-cut odour analysis. In figure 2 the GC-analysis is shown of an air sample in the neighbourhood of a rendering plant, showing a great number of VOCs; however almost all of them are hydrocarbons produced by cars and heating systems and sane other products, which do not contribute to the odour. Very small peaks of odorants are detected, which shows the difficult task of odour ana­ lysis with a general concentrating technique. Of course this analysis is far more relevant if emission gases are examined as is demonstrated in fi­ gure 3 (7). Part of these difficulties can be overcane if the odorants can." In Odour Prevention and Control of Organic Sludge and Livestock Farming. CRC Press, 1986. http://dx.doi.org/10.1201/9781482286311-75.

Ono, Kosuke, Yasunori Yamamoto, Masayoshi Mori, and Tetsuya Takada. "Experiment and Analysis on Isolation Condenser Simulator Using Pressurized Steam." In 2020 International Conference on Nuclear Engineering collocated with the ASME 2020 Power Conference. American Society of Mechanical Engineers, 2020. http://dx.doi.org/10.1115/icone2020-16842.

Cao, Huasong. "Simulation of Small Steam Generator Tube Break (SSGTB) in a Small Pressurized Water Reactor (SPWR)." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66637.

Jung, Gong H., Parikh Prashant, Jorge Penso, and Dong S. Kim. "Creep Damage Analysis of High Pressurized Steam Pipelines Using Omega Method." In ASME 2008 Pressure Vessels and Piping Conference. ASMEDC, 2008. http://dx.doi.org/10.1115/pvp2008-61662.

Henriksson, Mats, Johan Westin, Tord Granha¨ll, Lars Andersson, and Lars-Erik Bjerke. "Flow Instabilities and Main Steam Line Vibrations in a Pressurized Water Reactor." In 10th International Conference on Nuclear Engineering. ASMEDC, 2002. http://dx.doi.org/10.1115/icone10-22531.

Khokhlov, D. A., M. N. Zaichenko, K. V. Sterkhov, and K. A. Pleshanov. "Computational Model for High-Pressurized Heat Recovery Steam Generator Heat Transfer Study." In 2020 V International Conference on Information Technologies in Engineering Education ( Inforino ). IEEE, 2020. http://dx.doi.org/10.1109/inforino48376.2020.9111734.

Sterkhov, K. V., D. A. Khokhlov, K. A. Pleshanov, and M. N. Zaichenko. "High-Pressurized Heat Recovery Steam Generator for Combined Cycle Gas Turbine plant." In 2019 International Youth Conference on Radio Electronics, Electrical and Power Engineering (REEPE). IEEE, 2019. http://dx.doi.org/10.1109/reepe.2019.8708764.

Omar, Hossin, and Mohamed Elmnefi. "Simulations of Pressurized Fluidized Circulating Bed Based Combined Cycle (PFCB)." In ASME 2014 Power Conference. American Society of Mechanical Engineers, 2014. http://dx.doi.org/10.1115/power2014-32246.

Gou, Junli, Suizheng Qiu, Guanghui Su, and Dounan Jia. "Natural Circulation Characteristics of an Integral Pressurized Water Reactor." In 14th International Conference on Nuclear Engineering. ASMEDC, 2006. http://dx.doi.org/10.1115/icone14-89390.

Jiang, Huijing, Ning Bai, Huanfen Zhan, Feng Shen, Bin Gao, and Xuee Wang. "Small Modular Pressurized Water Reactors Combined With Conventional Thermal Power Plant." In 2017 25th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2017. http://dx.doi.org/10.1115/icone25-66690.

Sun, Peiwei, and Chong Wang. "Coordinated Control of a Small Pressurized Water Reactor." In 2018 26th International Conference on Nuclear Engineering. American Society of Mechanical Engineers, 2018. http://dx.doi.org/10.1115/icone26-81156.

Majumdar, S., W. J. Shack, D. R. Diercks, K. Mruk, J. Franklin, and L. Knoblich. Failure behavior of internally pressurized flawed and unflawed steam generator tubing at high temperatures -- Experiments and comparison with model predictions. Office of Scientific and Technical Information (OSTI), 1998. http://dx.doi.org/10.2172/573401.

Recknagle, Kurtis P., and Mohammad A. Khaleel. Modeling of Pressurized Electrochemistry and Steam-Methane Reforming in Solid Oxide Fuel Cells and the Effects on Thermal and Electrical Stack Performance. Office of Scientific and Technical Information (OSTI), 2009. http://dx.doi.org/10.2172/1000834.

Lee, S., and E. Carls. Measurement of alkali metal vapors and their removal from a pressurized fluidized-bed combustor process stream: Annual report, October 1987--September 1988. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/5966829.

Lee, S. H. D., and E. L. Carls. Measurement of alkali metal vapors and their removal from a pressuriz ed fluidized-bed combustor process stream: Annual report, October 1986--September 1987. Office of Scientific and Technical Information (OSTI), 1989. http://dx.doi.org/10.2172/6351627.