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Di Nora V, Fridman E, Nikitin E, Bilodid Y, Mikityuk K. Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part II: Methodology application. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108541] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Ponomarev A, Mikityuk K, Fridman E, Di Nora VA, Bubelis E, Schikorr M. Superphénix Benchmark Part II: Transient Results. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2021. [DOI: 10.1115/1.4051877] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
Abstract
Abstract
The paper presents a transient simulation phase of the new benchmark on a large sodium fast reactor (SFR). This phase of the benchmark is devoted to the modeling of selected operational transients performed during startup tests of the French SFR Superphénix. Six operational transients were selected for the analysis. The specifications of a simplified thermal hydraulic model equipped with point kinetics reactivity data and boundary conditions for the selected transients are given in the paper. The developed model contains a necessary thermal hydraulic description of the primary system components, assumptions to account for thermal expansion reactivity feedback from out-of-core structures, neutron kinetics parameters, power distribution, and reactivity coefficients. The neutronic input parameters were obtained with the help of the Monte Carlo code serpent during the first phase of the benchmark related to the static neutronic characterization of the core. In this study, the solution of the transient benchmark was obtained with three thermal hydraulic system codes, namely, TRACE, SIM-SFR, and ATHLET. The numerical results, compared to the available experimental data, exhibit a reasonable mutual agreement. Particular discrepancies between calculations and experiments could not be fully resolved. Therefore, a set of recommendations for achieving an improved agreement was proposed. In general, the proposed transient benchmark can be seen as an effective tool for validation and cross comparisons of system codes applied for safety analyses of SFRs, including approbation and comparison of different modeling features for thermal expansion of the out-of-core structures.
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Di Nora V, Fridman E, Nikitin E, Bilodid Y, Mikityuk K. Optimization of multi-group energy structures for diffusion analyses of sodium-cooled fast reactors assisted by simulated annealing – Part I: Methodology demonstration. ANN NUCL ENERGY 2021. [DOI: 10.1016/j.anucene.2021.108183] [Citation(s) in RCA: 3] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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Nikitin E, Fridman E, Mikityuk K, Radman S, Fiorina C. NEUTRONIC MODELLING OF THE FFTF CONTROL ROD WORTH MEASUREMENTS WITH DIFFUSION CODES. EPJ WEB OF CONFERENCES 2021. [DOI: 10.1051/epjconf/202124710017] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/14/2022] Open
Abstract
This paper presents an assessment of three deterministic core simulators with the focus on the neutronic performance in steady-state calculations of small Sodium cooled Fast Reactor cores. The selected codes are DYN3D, PARCS and the novel multi-physics solver GeN-Foam. By using these codes, the multi-group diffusion solutions are obtained for the selected twenty control rod worth measurements performed during the isothermal physics tests of the Fast Flux Test Facility (FFTF). The identical set of homogenized few-group cross sections applied in the calculations is generated with the Serpent Monte Carlo code. The numerical results are compared with each other as well as with the measured values. The obtained numerical results, such as the multiplication factors and control rod worth values, are in good agreement as compared to the experimental data. Furthermore, a comparison of the radial power distributions is presented between DYN3D, PARCS and GeN-Foam. Ultimately, the power distributions are compared to the full core Serpent solution, demonstrating an adequate performance of the selected deterministic tools. In overall, this study presents a verification and validation of the neutronic solvers applied by DYN3D, PARCS and GeN-Foam to steady-state calculations of SFR cores.
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Fridman E, Valtavirta V, Aufiero M. Nuclear data sensitivity and uncertainty analysis of critical VENUS-F cores with the Serpent Monte Carlo code. ANN NUCL ENERGY 2020. [DOI: 10.1016/j.anucene.2019.107196] [Citation(s) in RCA: 4] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/26/2022]
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Nikitin E, Fridman E. Modeling of the FFTF isothermal physics tests with the Serpent and DYN3D codes. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2019.06.058] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Bilodid Y, Fridman E, Kotlyar D, Shwageraus E. Explicit decay heat calculation in the nodal diffusion code DYN3D. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.07.045] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Nikitin E, Fridman E. Extension of the reactor dynamics code DYN3D to SFR applications – Part II: Validation against the Phenix EOL control rod withdrawal tests. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.016] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
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Drori T, Zilberman D, Fridman E, Churi C, Winkler H, Soudack M, Mor Y. An unusual radiologic appearance of Wilms tumor. Urol Case Rep 2018; 20:85-87. [PMID: 30035097 PMCID: PMC6052198 DOI: 10.1016/j.eucr.2018.07.009] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 05/13/2018] [Accepted: 07/06/2018] [Indexed: 11/24/2022] Open
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Nikitin E, Fridman E. Extension of the reactor dynamics code DYN3D to SFR applications – Part III: Validation against the initial phase of the Phenix EOL natural convection test. ANN NUCL ENERGY 2018. [DOI: 10.1016/j.anucene.2018.05.017] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Abu-Ghanem Y, Ramon J, Berger R, Kaver I, Fridman E, Leibowitz-Amit R, Dotan ZA. Positive surgical margin following radical nephrectomy is an independent predictor of local recurrence and disease-specific survival. World J Surg Oncol 2017; 15:193. [PMID: 29096642 PMCID: PMC5668980 DOI: 10.1186/s12957-017-1257-6] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Abstract] [Key Words] [Track Full Text] [Download PDF] [Figures] [Journal Information] [Subscribe] [Scholar Register] [Received: 09/02/2017] [Accepted: 10/15/2017] [Indexed: 11/10/2022] Open
Abstract
Background Positive surgical margins (PSM) are recognized as an adverse prognostic sign and are often associated with higher rates of local and systemic disease recurrence. The data regarding the oncological outcome for PSM following radical nephrectomy (RN) is limited. We examined the predictive factors for PSM and its influence on survival and site of recurrence in patients treated with RN for renal cell carcinoma (RCC). Methods Clinical, pathologic and follow-up data on 714 patients undergoing RN for kidney cancer were analyzed. Secondary analysis included 44 patients with metastatic RCC upon diagnosis who underwent cytoreductive nephrectomy (CRN). Univariate and multivariable logistic regression models were fit to determine clinicopathologic features associated with PSM. A Cox proportional-hazards regression model was used to test the independent effects of clinical and pathologic variables on survival. Results PSM was documented in 17 cases (2.4%). PSM were associated with tumour size, advanced pathologic stage (pT3 vs. ≤ pT2) and presence of necrosis. On multivariate analysis, cancer-specific survival (CSS) was associated with tumour stage, size, presence of necrosis and PSM. PSM was also associated with local recurrence but not distant metastasis or overall survival (OS). CSS and OS were comparable between the PSM and metastatic RCC groups, but significantly lower than the negative margin group. Conclusions The prevalence of PSM following RN is rare. Pathological data, including advanced stage (> pT2), tumour necrosis and tumour size, are associated with the presence of PSM. PSM is associated with tumour recurrence and CSS. Patients with PSM are a potential group for adjuvant therapy or for more careful and thorough follow-up following surgery.
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Nikitin E, Fridman E, Bilodid Y, Kliem S. New version of the reactor dynamics code DYN3D for Sodium cooled Fast Reactor analyses. KERNTECHNIK 2017. [DOI: 10.3139/124.110803] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
AbstractThe reactor dynamics code DYN3D being developed at the Helmholtz-Zentrum Dresden-Rossendorf is currently under extension for Sodium cooled Fast Reactor analyses. This paper provides an overview on the new version of DYN3D to be used for SFR core calculations. The current article shortly describes the newly implemented thermal mechanical models, which can account for thermal expansion effects of the reactor core. Furthermore, the methodology used in Sodium cooled Fast Reactor analyses to generate homogenized few-group cross sections is summarized. The conducted and planned verification and validation studies are briefly presented. Related publications containing more detailed descriptions are outlined for the completeness of this overview.
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Fridman E, Shwageraus E, Galperin A. Efficient Generation of One-Group Cross Sections for Coupled Monte Carlo Depletion Calculations. NUCL SCI ENG 2017. [DOI: 10.13182/nse07-34] [Citation(s) in RCA: 20] [Impact Index Per Article: 2.9] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
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Fridman E, Shwageraus E, Galperin A. Fertile-Free Fuels in Pressurized Water Reactors: Design Challenges and Solutions. NUCL TECHNOL 2017. [DOI: 10.13182/nt07-a3810] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
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Kotlyar D, Fridman E, Shwageraus E. One-Group Cross-Section Generation for Monte Carlo Burnup Codes: Multigroup Method Extension and Verification. NUCL SCI ENG 2017. [DOI: 10.13182/nse14-59] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/12/2022]
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Amit M, Na'ara S, Leider-Trejo L, Binenbaum Y, Kulish N, Fridman E, Shabtai-Orbach A, Wong RJ, Gil Z. Upregulation of RET induces perineurial invasion of pancreatic adenocarcinoma. Oncogene 2017; 36:3232-3239. [PMID: 28092668 DOI: 10.1038/onc.2016.483] [Citation(s) in RCA: 35] [Impact Index Per Article: 5.0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 07/25/2016] [Revised: 10/14/2016] [Accepted: 11/17/2016] [Indexed: 02/06/2023]
Abstract
Tumor spread along nerves, a phenomenon known as perineurial invasion, is common in various cancers including pancreatic ductal adenocarcinoma (PDAC). Neural invasion is associated with poor outcome, yet its mechanism remains unclear. Using the transgenic Pdx-1-Cre/KrasG12D /p53R172H (KPC) mouse model, we investigated the mechanism of neural invasion in PDAC. To detect tissue-specific factors that influence neural invasion by cancer cells, we characterized the perineurial microenvironment using a series of bone marrow transplantation (BMT) experiments in transgenic mice expressing single mutations in the Cx3cr1, GDNF and CCR2 genes. Immunolabeling of tumors in KPC mice of different ages and analysis of human cancer specimens revealed that RET expression is upregulated during PDAC tumorigenesis. BMT experiments revealed that BM-derived macrophages expressing the RET ligand GDNF are highly abundant around nerves invaded by cancer. Inhibition of perineurial macrophage recruitment, using the CSF-1R antagonist GW2580 or BMT from CCR2-deficient donors, reduced perineurial invasion. Deletion of GDNF expression by perineurial macrophages, or inhibition of RET with shRNA or a small-molecule inhibitor, reduced perineurial invasion in KPC mice with PDAC. Taken together, our findings show that RET is upregulated during pancreas tumorigenesis and its activation induces cancer perineurial invasion. Trafficking of BM-derived macrophages to the perineurial microenvironment and secretion of GDNF are essential for pancreatic cancer neural spread.
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Leibowitz-Amit R, Israel A, Gal M, Atenafu E, Symon Z, Portnoy O, Laufer M, Dotan Z, Ramon J, Avni D, Fridman E, Berger R. Association between the Absolute Baseline Lymphocyte Count and Response to Neoadjuvant Platinum-based Chemotherapy in Muscle-invasive Bladder Cancer. Clin Oncol (R Coll Radiol) 2016; 28:790-796. [DOI: 10.1016/j.clon.2016.07.007] [Citation(s) in RCA: 17] [Impact Index Per Article: 2.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Received: 03/03/2016] [Revised: 06/06/2016] [Accepted: 06/22/2016] [Indexed: 01/04/2023]
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Bilodid Y, Kotlyar D, Shwageraus E, Fridman E, Kliem S. Hybrid microscopic depletion model in nodal code DYN3D. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2016.02.012] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.3] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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Kliem S, Bilodid Y, Fridman E, Baier S, Grahn A, Gommlich A, Nikitin E, Rohde U. The reactor dynamics code DYN3D. KERNTECHNIK 2016. [DOI: 10.3139/124.110692] [Citation(s) in RCA: 14] [Impact Index Per Article: 1.8] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
Abstract
Abstract
The article provides an overview on the code DYN3D which is a three-dimensional core model for steady-state, dynamic and depletion calculations in reactor cores with quadratic or hexagonal fuel assembly geometry being developed by the Helmholtz-Zentrum Dresden-Rossendorf for more than 20 years. The current paper gives an overview on the basic DYN3D models and the available code couplings. The verification and validation status is shortly outlined. The paper concludes with the current developments of the DYN3D code. For more detailed information the reader is referred to the publications cited in the corresponding chapters.
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Shvero A, Zilberman D, Mor Y, Kaver I, Fridman E, Portnoy O, Laufer M, Berger R, Ramon J, Dotan Z. MP41-19 LOCAL RECURRENCE AFTER PARTIAL NEPHRECTOMY FOR PRIMARY RENAL TUMORS – INCIDENCE, RISK FACTORS AND ONCOLOGIC FOLLOW-UP. J Urol 2016. [DOI: 10.1016/j.juro.2016.02.186] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Friedman B, Dekel Y, Tubaro A, Sidi A, Shalva B, Baniel J, Kedar D, Colombo L, Engelshtein D, Fridman E, Klein I, Jeshurun M, Nerotski B, Zolotrayov D, Malchi N, Palou Redorta J, Wirth G, Leibovitch I, Witjes F. PD11-05 THE CHEMOABLATIVE EFFECT OF VESIGEL INSTILLATION IN PATIENTS WITH NMIBC – PRELIMINARY RESULTS. J Urol 2016. [DOI: 10.1016/j.juro.2016.02.845] [Citation(s) in RCA: 3] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/22/2022]
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Baldova D, Fridman E, Shwageraus E. High Conversion Th–U233 fuel for current generation of PWRs: Part III – Fuel availability and utilization considerations. ANN NUCL ENERGY 2016. [DOI: 10.1016/j.anucene.2015.10.006] [Citation(s) in RCA: 6] [Impact Index Per Article: 0.8] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Nikitin E, Fridman E, Mikityuk K. On the use of the SPH method in nodal diffusion analyses of SFR cores. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.06.007] [Citation(s) in RCA: 22] [Impact Index Per Article: 2.4] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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Bilodid Y, Kotlyar D, Margulis M, Fridman E, Shwageraus E. Spectral history model in DYN3D: Verification against coupled Monte-Carlo thermal-hydraulic code BGCore. ANN NUCL ENERGY 2015. [DOI: 10.1016/j.anucene.2015.03.030] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/25/2022]
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