Relevant bibliographies by topics / BWR1

Contents

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

Academic literature on the topic 'BWR1'

Author: Grafiati
Published: 6 September 2023
Last updated: 19 July 2025

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Journal articles on the topic "BWR1"

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Nilsson, Tina, Anna Sjöblom, Maria G. Masucci, and Lars Rymo. "Viral and Cellular Factors Influence the Activity of the Epstein-Barr Virus BCR2 and BWR1 Promoters in Cells of Different Phenotype." Virology 193, no. 2 (1993): 774–85. http://dx.doi.org/10.1006/viro.1993.1186.

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LU, TIEN-FU. "MODELING FOR STOCKPILE OPERATIONS ASSOCIATED WITH BULK SOLID MATERIALS USING BUCKET WHEEL RECLAIMER." International Journal of Information Acquisition 07, no. 04 (2010): 357–73. http://dx.doi.org/10.1142/s0219878910002270.

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Bucket wheel reclaimer (BWR) is one of the main equipment which has been widely used for stacking/reclaiming bulk materials (i.e., iron ore and coal) in ports, iron-steel plants, coal storages, and power stations onto/from stockpiles by mining industry. Generally speaking, current BWRs are mostly manually operated, remotely operated, or automated to simply follow predefined trajectory patterns for stacking and reclaiming operations. BWRs are indeed very large in size, heavy in weight, expensive in price, and slow in motion. It is commonly agreed in the industry that the current stacking/reclai
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Altiok, E., J. Minarovits, L. F. Hu, B. Contreras-Brodin, G. Klein, and I. Ernberg. "Host-cell-phenotype-dependent control of the BCR2/BWR1 promoter complex regulates the expression of Epstein-Barr virus nuclear antigens 2-6." Proceedings of the National Academy of Sciences 89, no. 3 (1992): 905–9. http://dx.doi.org/10.1073/pnas.89.3.905.

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Olvera-Guerrero, Omar Alejandro, Alfonso Prieto-Guerrero, and Gilberto Espinosa-Paredes. "A Novel Nonlinear BWR Stability Indicator Based on the Sample Entropy." Science and Technology of Nuclear Installations 2018 (November 1, 2018): 1–13. http://dx.doi.org/10.1155/2018/9852925.

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BWRs are thus far the simplest energy systems to transform fission energy into electrical power. However, there are still many aspects in their operation that, under certain conditions, may induce BWR unstable behavior. The default indicator to study BWR unstable behavior is the Decay Ratio (DR). However, due to the fact that BWRs show very complex responses under instability and responses that may even be chaotic, the DR might not be a suitable choice to rely on to accommodate for such intricate behavior. In this work a novel methodology based on the Sample entropy (SampEn) and the noise-assi
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LANGE, CARSTEN, DIETER HENNIG, and ANTONIO HURTADO. "A NOVEL RESULT IN THE FIELD OF NONLINEAR STABILITY ANALYSIS OF BOILING WATER REACTORS." International Journal of Bifurcation and Chaos 22, no. 02 (2012): 1250041. http://dx.doi.org/10.1142/s0218127412500411.

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The nonlinear stability analysis of boiling water nuclear reactors (BWRs) is conducted with the aid of so-called advanced, well validated, system codes and an advanced reduced order model to build a detailed mathematical understanding of the BWR behavior in the practical relevant parameter space. In the last years, the existence of Hopf-bifurcation points was confirmed by some researchers. In the framework of this paper, a parameter region was analyzed in which the coexistence of different stability states is realized. As a novel result, we found a parameter region in which stable fixed points
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Zohuri, Bahman. "Enhancing Nuclear Reactor Safety through ICE Digital Systems and Cyber Integration." Journal of Material Sciences & Manufacturing Research 5, no. 1 (2024): 1–6. http://dx.doi.org/10.47363/jmsmr/2024(5)164.

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This article examines the imperative of enhancing nuclear reactor safety through the Integration of Instrumentation, Control, and Electrical) Digital (ICE) Systems and cybersecurity measures. Focused on advancements within Boiling Water Reactors (BWRs), particularly the BWRX-300, the discussion emphasizes the transformative impact of digital technology on safety protocols. ICE Digital Systems contribute to real-time monitoring, predictive maintenance, and remote operation, optimizing reactor performance. Simultaneously, robust cybersecurity measures are integrated to safeguard against potentia
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Cui, Weihua, Bao Song, Chao Fu, and Hui Wang. "Effect of pitch on mechanical properties of braided wire rope under winding and traction condition." Journal of Physics: Conference Series 2355, no. 1 (2022): 012080. http://dx.doi.org/10.1088/1742-6596/2355/1/012080.

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Abstract In the tension stringing construction process of power transmission and transformation engineering, the braided wire ropes (BWRs) are in the state of winding and stretching when passing through the friction drum. Pitch is an important structural parameter of BWRs, which directly influences the mechanical behaviors under these conditions. Based on the YS9-8×19 wire rope, this project studies the effect of the rope strand pitch on the curvature and winding from both qualitative and quantitative aspects. Qualitative analysis initially explores the effect of the pitch on the mechanical be
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Mertyurek, Ugur, Riley Cumberland, and William A. Wieselquist. "Core Physics Characteristics of Extended Enrichment and High Burnup Boiling Water Reactor Fuel." Journal of Nuclear Engineering 6, no. 1 (2025): 4. https://doi.org/10.3390/jne6010004.

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This paper presents the highlights of boiling water reactor (BWR) core physics studies performed at Oak Ridge National Laboratory as part of a series of studies conducted to compare low-enriched uranium (LEU) with LEU+ fuel. The studies analyzed isotopic fuel content, lattice parameters (Phase 1), and core physics (Phase 2) to identify challenges in operation, storage, and transportation for BWRs and pressurized water reactors (PWRs). Because of a lack of publicly available lattice and core designs for modern BWR fuel assemblies and reactor cores, several optimized lattice designs were generat
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Macdonald, Digby D., and George R. Engelhardt. "A Critical Review of Radiolysis Issues in Water-Cooled Fission and Fusion Reactors: Part II, Prediction of Corrosion Damage in Operating Reactors." Corrosion and Materials Degradation 3, no. 4 (2022): 694–758. http://dx.doi.org/10.3390/cmd3040038.

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The radiolysis of water is a significant cause of corrosion damage in the primary heat transport systems (PHTSs) of water-cooled, fission nuclear power reactors (BWRs, PWRs, and CANDUs) and is projected to be a significant factor in the evolution of corrosion damage in future fusion reactors (e.g., the ITER that is currently under development). In Part I of this two-part series, we reviewed the proposed mechanisms for the radiolysis of water and demonstrate that radiolysis leads to the formation of a myriad of oxidizing and reducing species. In this Part II, we review the role that the radioly
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Harder, James W., Jing Ma, Pascale Alard та ін. "Male microbiota-associated metabolite restores macrophage efferocytosis in female lupus-prone mice via activation of PPARγ/LXR signaling pathways". Journal of Leukocyte Biology 113, № 1 (2023): 41–57. http://dx.doi.org/10.1093/jleuko/qiac002.

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Abstract Systemic lupus erythematosus development is influenced by both sex and the gut microbiota. Metabolite production is a major mechanism by which the gut microbiota influences the immune system, and we have previously found differences in the fecal metabolomic profiles of lupus-prone female and lupus-resistant male BWF1 mice. Here we determine how sex and microbiota metabolite production may interact to affect lupus. Transcriptomic analysis of female and male splenocytes showed genes that promote phagocytosis were upregulated in BWF1 male mice. Because patients with systemic lupus erythe
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Dissertations / Theses on the topic "BWR1"

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Raub, Sebastian. "Transient behaviour in a BWR with Hafnium Cladding : Feasibility study of using BWRs as Higher Actinide Burners at the Example of Ringhals I." Thesis, KTH, Skolan för teknikvetenskap (SCI), 2011. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-38189.

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Transmutation of transuranic elements is of interest to lower storage unit cost and long-term radiotoxicity. To make use of existing infrastructure, the deployment of Boiling Water Reactors (BWRs) with hafnium cladding and Mixed Oxide (MOX) fuel was proposed, resulting in a hardening of the neutron spectrum. This work tests varying spatial fuel configurations for maximal burn-up, using Serpent, and study their behaviour in common accident scenarios, simulated by a coupled TRACE/PARCS software suite. To this end, we provide a software solution, which serves to transfer Serpent output of a user
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Chun, John Hwan. "Modeling of BWR water chemistry." Thesis, Massachusetts Institute of Technology, 1990. http://hdl.handle.net/1721.1/13660.

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Soma, Kovács István. "Simplified Simulator for BWR Instabilities." Thesis, KTH, Fysik, 2017. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-210626.

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Ferroni, Paolo Ph D. Massachusetts Institute of Technology. "Steady state thermal hydraulic analysis of hydride fueled BWRs." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41263.

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Includes bibliographical references (p. 205-208).<br>Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2006.<br>(cont.) Since the results obtained in the main body of the analysis account only for thermal-hydraulic constraints, an estimate of the power reduction due to the application of neutronic constraints is also performed. This investigation, focused only on the "New Core" cases, is coupled with an increase of the thickness of the gap separating adjacent bundles from 2 to 5 mm. Under these more conservative conditions, the power gain percentag
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Morra, Paolo. "Design of annular fuel for high power density BWRs." Thesis, Massachusetts Institute of Technology, 2004. http://hdl.handle.net/1721.1/34448.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, February 2005.<br>Includes bibliographical references (p. 94).<br>Enabling high power density in the core of Boiling Water Reactors (BWRs) is economically profitable for existing or new reactors. In this work, we examine the potential for increasing the power density in BWR plants by switching from the current solid fuel to annular fuel cooled both on its inside and outside surfaces. The GE 8x8 bundle dimensions and fuel to moderator ratio are preserved as a reference to enable applications in existing reactors
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Karahan, Aydin. "An evolutionary fuel assembly design for high power density BWRs." Thesis, Massachusetts Institute of Technology, 2006. http://hdl.handle.net/1721.1/41304.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, February 2007.<br>Includes bibliographical references (p. 138-140).<br>An evolutionary BWR fuel assembly design was studied as a means to increase the power density of current and future BWR cores. The new assembly concept is based on replacing four traditional assemblies and large water gap regions with a single large assembly. The traditional BWR cylindrical UO2-fuelled Zr-clad fuel pin design is retained, but the pins are arranged on a 22x22 square lattice. There are 384 fuel pins with 9.6 mm dia
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Gajev, Ivan. "Sensitivity and Uncertainty Analysis of BWR Stability." Licentiate thesis, KTH, Kärnkraftsäkerhet, 2010. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-26387.

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Best Estimate codes are used for licensing, but with conservative assumptions. It is claimed that the uncertainties are covered by the conservatism of the calculation. As Nuclear Power Plants are applying for power up-rates and life extension, evaluation of the uncertainties could help improve the performance, while staying below the limit of the safety margins.   Given the problem of unstable behavior of Boiling Water Reactors (BWRs), which is known to occur during operation at certain power and flow conditions, it could cause SCRAM and decrease the economic performance of the plant. Performi
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Melara, San Román José. "PREDICTIVE METHODS FOR STABILITY MARGIN IN BWR." Doctoral thesis, Universitat Politècnica de València, 2016. http://hdl.handle.net/10251/61307.

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[EN] Power and flow oscillations in a BWR are very undesirable. One of the major concerns is to ensure, during power oscillations, compliance with GDC 10 and 12. GDC 10 requires that the reactor core be designed with appropriate margin to assure that specified acceptable fuel design limits will not be exceeded during any condition of normal operation, including the effects of anticipated operational occurrences. GDC 12 requires assurance that power oscillations which can result in conditions exceeding specified acceptable fuel design limits are either not possible or can be reliably and readil
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Hu, Rui Ph D. Massachusetts Institute of Technology. "Stability analysis of natural circulation in BWRs at high pressure conditions." Thesis, Massachusetts Institute of Technology, 2007. http://hdl.handle.net/1721.1/46431.

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Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Science and Engineering, 2007.<br>Includes bibliographical references (leaves 112-115).<br>At rated conditions, a natural circulation boiling water reactor (NCBWR) depends completely on buoyancy to remove heat from the reactor core. This raises the issue of potential unstable flow. oscillations. The objective of this work is to assess the characteristics of stability in a NCBWR at rated conditions, and the sensitivity to design and operating conditions in comparison to previous BWRs. Two kinds of instabilities, namely Ledin
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Luszczek, Karol. "Validation and Benchmarking of Westinghouse BWR lattice physics methods." Thesis, KTH, Reaktorteknologi, 2015. http://urn.kb.se/resolve?urn=urn:nbn:se:kth:diva-180563.

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A lattice physics code is a vital tool, forming a base of reactor coreanalysis. It enables the neutronic properties of the fuel assembly to becalculated and generates a proper set of data to be used by a 3-D full coresimulator. Due to advancement and complexity of modern Boiling WaterReactor assembly designs, a new deterministic lattice physics codeis being developed at Westinghouse Sweden AB, namely PHOENIX5.Each time a new code is written, its methodology of solving the neutrontransport equation, has to be validated to make sure it providesreliable output. In a wake of preparation for PHOENI
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Books on the topic "BWR1"

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Jones, Bethan Wyn. Bwrw blwyddyn. Gwasg Gwynedd, 1997.

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Etherton, Roy. Bwrw lliwiau. Gwasg Cambria, 1991.

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1935-, Owen William, and Ysgol Carreg-lefn, eds. Bwrw cyfrif 'rôl canrif. Corff Llywodraethol Ysgol Gymuned Carreg-lefn, 1999.

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Kikō, Genshiryoku Anzen Kiban. Teishiji reberu 2PSA no kentō (BWR). Genshiryoku Anzen Kiban Kikō, 2005.

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Theofanous, T. G. Performance of the liquid reactivity control system in BWRs. Division of Regulatory Applications, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, 1989.

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Kikō, Genshiryoku Anzen Kiban. Reberu 2 PSA shuhō no seibi (BWR). Genshiryoku Anzen Kiban Kikō, 2005.

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U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation, ed. BWR and PWR off-normal event descriptions. Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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U.S. Nuclear Regulatory Commission. Office of Nuclear Reactor Regulation. Division of Licensee Performance and Quality Evaluation, ed. BWR and PWR off-normal event descriptions. Division of Licensee Performance and Quality Evaluation, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, 1987.

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Kikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). Genshiryoku Anzen Kiban Kikō, 2008.

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Kikō, Genshiryoku Anzen Kiban, ed. Jishinji reberu 2 PSA no kaiseki (BWR). Genshiryoku Anzen Kiban Kikō, 2008.

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Book chapters on the topic "BWR1"

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Radvany, R. M., J. van Munster, S. Nakata, et al. "Antigen Society #14 Report (B40 CREG, BW60, BW61, BW41, BW48, B13)." In Immunobiology of HLA. Springer New York, 1989. http://dx.doi.org/10.1007/978-1-4612-3552-1_36.

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Cattant, François. "BWRs Cracking." In Materials Ageing in Light-Water Reactors. Springer International Publishing, 2022. http://dx.doi.org/10.1007/978-3-030-85600-7_23.

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Prince, Robert. "Radiological Aspects of BWR Systems." In Radiation Protection at Light Water Reactors. Springer Berlin Heidelberg, 2012. http://dx.doi.org/10.1007/978-3-642-28388-8_3.

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Laundy, Godfrey J., Marilyn S. Pollack, Martin G. Guttridge, and Peter T. Klouda. "Antigen Society #8 Report (Bw70, Bw71, Bw72)." In Immunobiology of HLA. Springer New York, 1989. http://dx.doi.org/10.1007/978-1-4612-3552-1_28.

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Reynolds, R. S. "A BWR Fuel Channel Tracking System." In Artificial Intelligence and Other Innovative Computer Applications in the Nuclear Industry. Springer US, 1988. http://dx.doi.org/10.1007/978-1-4613-1009-9_75.

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Guttridge, M. G., G. J. Laundy, and P. T. Klouda. "Biochemical Variants of the Bw70 Antigen (Bw71, Bw72)." In Immunobiology of HLA. Springer New York, 1989. http://dx.doi.org/10.1007/978-1-4612-3552-1_71.

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Kim, Young-Jin, and Peter L. Andresen. "Protective Insulated Coating for SCC Mitigation in BWRs." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_126.

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Kim, Young-Jin, and Peter L. Andresen. "Protective Insulated Coating for SCC Mitigation in BWRs." In 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors. John Wiley & Sons, Inc., 2012. http://dx.doi.org/10.1002/9781118456835.ch218.

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Lutz, Dan, Yang-Pi Lin, Randy Dunavant, et al. "Hydriding Induced Corrosion Failures in BWR Fuel." In Zirconium in the Nuclear Industry: 17th Volume. ASTM International, 2014. http://dx.doi.org/10.1520/stp154320120198.

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Kim, Young-Jin, Peter L. Andresen, and Samson Hettiarachchi. "Use of Noble Metal Nanopartice for SCC Mitigation in BWRs." In Proceedings of the 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems — Water Reactors. Springer International Publishing, 2011. http://dx.doi.org/10.1007/978-3-319-48760-1_119.

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Conference papers on the topic "BWR1"

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Hettiarachchi, S. "Worldwide BWR Chemistry Performance with Noble Metal Chemical Addition." In CORROSION 2002. NACE International, 2002. https://doi.org/10.5006/c2002-02508.

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Abstract Noble metal chemical addition (NMCA) is an industry-wide accepted approach for potential intergranular stress corrosion crack (IGSCC) mitigation of boiling water reactor (BWR) internals. NMCA has been successfully applied in 26 BWRs worldwide. Those BWRs that have applied NMCA and used low levels of feedwater hydrogen have achieved the HWC specification potential of -230 mV(SHE) without the long-term operating dose rate increases due to partitioning of N16 into the steam phase. NMCA is a simpler method of applying noble metal on to BWR internals surfaces using reactor water as the tra
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Jones, Robin L. "Prevention of Stress Corrosion Cracking in Boiling Water Reactors." In CORROSION 1990. NACE International, 1990. https://doi.org/10.5006/c1990-90483.

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Abstract Intergranular Stress Corrosion Cracking (IGSCC) adjacent to girth welds in stainless steel piping systems has been a serious problem in Boiling Water Reactor (BWR) plants in the U.S. for more than a decade. Recent observations suggest that IGSCC also may limit the service life of many reactor internals in BWRs. A major research and development program on BWR pipe cracking was cofunded by EPRI, GE, and the BWR Owners Group for IGSCC Research between 1979 and 1988 and a similar program on reactor internals has just begun. The pipe cracking remedies that are being used in U.S. BWRs are d
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Hettiarachchi, S., R. L. Cowan, R. J. Law, W. D. Miller, and T. P. Diaz. "Noble Metal Chemical Addition for IGSCC Mitigation of BWRs – Field Successes." In CORROSION 2000. NACE International, 2000. https://doi.org/10.5006/c2000-00184.

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Abstract Noble metal chemical addition (NMCA) technology has been successfully used to improve the efficacy of hydrogen water chemistry (HWC) in mitigating intergranular stress corrosion cracking (IGSCC) of BWR internals. The use of NMCA technology in combination with low levels of feedwater hydrogen enables to achieve the IGSCC mitigation potential of -230 mV(SHE) of boiling water reactor (BWR) internals without the undesirable operating dose rate increases due to partitioning of N16 into the steam phase. NMCA is a simpler method of applying noble metal on to BWR internals surfaces using reac
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Kassen, W. R., and D. Cubicciotti. "Proposed Guidelines for Implementing ECP Measurements in Boiling Water Reactors." In CORROSION 1990. NACE International, 1990. https://doi.org/10.5006/c1990-90485.

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Abstract Intergranular stress corrosion cracking (IGSCC) in boiling water reactor (BWR) recirculating water piping systems can be controlled by sufficient hydrogen addition to the feedwater to reduce the piping electrochemical potential (ECP) to less than -230 millivolts, SHE. Actual practice has shown that different BWR plants often manifest significantly different ECP responses to a given rate of hydrogen addition. There is no means for quantitatively predicting this behavior; therefore, continuous ECP monitoring has been recommended to assure the desired level of IGSCC protection is maintai
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Kim, Young-Jin, Peter L. Andresen, Samson Hettiarachchi, and Thomas P. Diaz. "Hydrothermal Formation and Distribution of Noble Metal Particles on Type 304 SS in High Temperature Water." In CORROSION 2007. NACE International, 2007. https://doi.org/10.5006/c2007-07604.

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Abstract Many boiling water nuclear reactors (BWRs) throughout the world have applied the NobleChemTM (or noble metal chemical addition: NMCA) process just before end-of-cycle shutdown or during a mid-cycle shutdown to mitigate the stress corrosion cracking (SCC) of structural materials in BWRs. The first Online NMCA (OLNC) plant demonstration was successfully completed during the summer of 2005 while the reactor was in power operation. When injected into BWR environments, the noble metal particles deposit on Type 304 stainless steel surfaces and reduce the corrosion potential, which decreases
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Indig, M. E., J. Lawrence Nelson, and G. P. Wozadlo. "Investigation of the Protection Potential against IASCC." In CORROSION 1992. NACE International, 1992. https://doi.org/10.5006/c1992-92071.

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Abstract Environmentally induced cracking of components exposed to the radiation and high-temperature aqueous environment of a light water reactor (LWR) is known as irradiation-assisted stress corrosion cracking (IASCC). In boiling water reactors (BWRs) annealed austenitic stainless steels have a threshold level of irradiation damage. Above a fluence level of 5 x 1020n/cm2, these alloys are susceptible to cracking in the normal BWR core environment. Below this threshold value, laboratory stress corrosion tests of irradiated material have not indicated cracking over a range of corrosion potenti
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Williams, Steve, Jeremie Varnam, and Dave Morgan. "Brunswick Nuclear Plant IGSCC Mitigation Strategy and Monitoring." In CORROSION 2015. NACE International, 2015. https://doi.org/10.5006/c2015-05822.

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Abstract Reduction of electrochemical corrosion potential (ECP) of Boiling Water Reactor (BWR) vessel and internals is essential for mitigating intergranular stress corrosion cracking (IGSCC). Hydrogen water chemistry in moderate concentrations (HWC-M) or at reduced injection rates with noble metals are IGSCC mitigation strategies employed by BWRs. In-vessel lower plenum ECP measurements have been obtained during operating conditions for BWRs utilizing normal water chemistry, HWC-M and first generation noble metals. ECP monitoring for BWRs with second generation has been limited to probes moun
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Tachibana, Masahiko, Kazushige Ishida, Yoichi Wada, Ryosuke Shimizu, and Nobuyuki Ota. "Cathodic Polarization Properties of Hydrogen Peroxide and the Effect on Electrochemical Corrosion Potential Calculation under Simulated BWR Environment." In CORROSION 2013. NACE International, 2013. https://doi.org/10.5006/c2013-02155.

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Abstract Hydrogen peroxide (H2O2) is the most important oxidant to determine the corrosive environment of boiling water reactors (BWRs). Since H2O2 is unstable at high temperature and electrochemical measurement in high purity water is difficult, H2O2 polarization characteristics in the BWR environment are not known well especially at less than 10 ppb. Cathodic polarization curves of the H2O2 were measured in simulated BWR conditions at 553 K over range of 1 to 1000 ppb. A polytetrafluoroethylene chamber was set in a circulating autoclave to reduce decomposition of H2O2, and the potential step
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Indig, M. E., J. L. Nelson, and G. Taylor. "Electrochemical Measurements and Modeling Predictions in BWRs under Various Operating Conditions." In CORROSION 1990. NACE International, 1990. https://doi.org/10.5006/c1990-90484.

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Abstract One important issue for providing life extension to operating boiling water nuclear reactors is the control of stress corrosion cracking in all sections of the primary coolant circuit. This paper links experimental and theoretical methods that provide understanding and measurements of the critical parameter, the electrochemical potential (ECP), and its application to determining crack growth rates among and within the family of BWRs. Measurement of in-core ECP required the development of a new family of radiation-resistant sensors. With these sensors, ECPs were measured in the core an
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Andresen, Peter L., and Tom Angeliu. "The Effect of in-situ Noble Metal Chemical Addition on Crack Growth Rate Behavior of Structural Materials in 288°C Water." In CORROSION 1996. NACE International, 1996. https://doi.org/10.5006/c1996-96084.

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Abstract Stress corrosion cracking (SCC), especially in existing boiling water reactor (BWR) components, is most effectively accomplished by reducing the corrosion potential. This was successfully demonstrated by adding hydrogen to BWR water, which reduced oxidant concentration and corrosion potential by recombining with the radiolytically formed oxygen and hydrogen peroxide. However, reduction in the corrosion potential for some vessel internals is difficult, and others require high hydrogen addition rates, which results in an increase in the main steam radiation level from volatile N16. Nobl
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Reports on the topic "BWR1"

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Ridens, Simons, and Brun. PR-316-15606-Z01 Equations of State Comparison for Pipeline Compressor Applications. Pipeline Research Council International, Inc. (PRCI), 2016. http://dx.doi.org/10.55274/r0010873.

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In order to have an improved understanding of the applicability of standard EOS in pipeline applications, a set of gas physical property tests were undertaken with sweet and sour natural gas and CO2 mixtures at typical pipeline compositions and conditions, including new high pressure dense phase applications. Specific gas properties tested include gas density (?), specific heat at constant volume (cv), and speed of sound (c or SOS). These results were compared to several of the most commonly used EOS, including NIST, GERG, AGA8, PR, SRK and BWRS, which were also compared to each other.
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A. Alsaed. BWR AXIAL PROFILE. Office of Scientific and Technical Information (OSTI), 2005. http://dx.doi.org/10.2172/862029.

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J. Huffer. BWR AXIAL PROFILE. Office of Scientific and Technical Information (OSTI), 2004. http://dx.doi.org/10.2172/862152.

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Lawing, Chase, Scott Palmtag, and Mehdi Asgari. BWR Progression Problems. Office of Scientific and Technical Information (OSTI), 2021. http://dx.doi.org/10.2172/1838995.

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Tan, C. P., and G. Bagchi. BWR steel containment corrosion. Office of Scientific and Technical Information (OSTI), 1996. http://dx.doi.org/10.2172/219387.

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Yoon, Su Jong. High Fidelity BWR Fuel Simulations. Office of Scientific and Technical Information (OSTI), 2016. http://dx.doi.org/10.2172/1364486.

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Sutherland, W., M. Alamgir, J. Findlay, and W. Hwang. BWR Full Integral Simulation Test (FIST) Phase II test results and TRAC-BWR model qualification. Office of Scientific and Technical Information (OSTI), 1985. http://dx.doi.org/10.2172/6349740.

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Cheng, L. Y., D. Diamond, and Gilad Raitses, Arnold Aronson Arantxa Cuadra. Trace Assessment for BWR ATWS Analysis. Office of Scientific and Technical Information (OSTI), 2010. http://dx.doi.org/10.2172/1013471.

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Ott, L. J. (Boiling water reactor (BWR) CORA experiments). Office of Scientific and Technical Information (OSTI), 1990. http://dx.doi.org/10.2172/6434331.

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D.P. Henderson and D.A. Salmon. Disposal Critcality Analysis Methodology: BWR Benchmarks. Office of Scientific and Technical Information (OSTI), 1999. http://dx.doi.org/10.2172/840675.

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