Sparks Mary, DePriest K., Vehar David
Published: 2018
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Cite this document
Get the latest information on databases, benchmark studies, techniques, and standardization of radiation metrology and regulatory information related to reactor dosimetry.
Learn more about modern technologies used in radiation imaging and the development of radiation instrumentation. Plus you’ll get over 50 peer-reviewed papers covering related new work in:
– Research/test reactor and accelerator dosimetry
– Cross sections, nuclear data, and uncertainties
– Reactor surveillance and plant life extension
– Adjustments, intercomparisons, and benchmarks
– Experimental techniques
– Transport calculations
Researchers, educators, manufacturers, regulators, and industry and utilities workers will benefit from this important research presented at the Sixteenth International Symposium on Reactor Dosimetry (ISRD) held in May 2017.
Design of Separated Element Reflector Experiments in CROCUS: PETALE
Vincent Lamirand, Gregory Perret, Stefan Radman, Daniel Siefman, Pavel Frajtag, Mathieu Hursin, Adrien Gruel, Pierre Leconte, Patrick Blaise, Andreas Pautz
Shielding and Activation Studies for the MYRRHA Research Reactor
Stefan Müller, Anna Ferrari, Jörg Konheiser
Neutron and Gamma-Ray Radiation Environments for the Annular Core Research Reactor
Edward Parma
Testing of the Retrospective Dosimetry Procedure Based on Niobium Extraction from VVER-1000 Cladding Material Samples after Their Irradiation in Research Reactor
Viacheslav Kochkin, Natalia Dmitrieva, Alexandr Reshetnikov, Dmitry Erak, Yuriy Pesnya, Vladimir Nasonov
Experiment-Based and Numerical Estimation Analysis of Neutron Field Performance in the In-Core Irradiation Positions and in the Lateral Blanket of the BOR-60 Reactor
Elena Lebedeva, Yury Naboishchikov, Anatoly Tellin, Dimitry Ryazanov
Fast Two-Parametric Spectrometric System for Experimental MSR/FHR Reactor Dosimetry
Zdeněk Matěj, Michal Košt´ál, Filip Mravec, Martin Pavelek, Ondřej Herman, Martin Veškrna, Václav Přenosil, František Cvachovec, Evžen Losa
1-MeV Equivalent Silicon Damage Studies at the White Sands Missile Range Fast Burst Reactor
Thomas Flanders, Mary Sparks
Establishment of CORONA Academy as Common Source of Knowledge in the Area of VVER Technology
Mladen Mitev, Mariya Manolova, Lyubomir Pironkov
Results of a New Evaluation of the Neutron Standards
Allan Carlson, Vladimir Pronyaev, Roberto Capote, Gerald Hale, Ignacio Duran, Franz-Josef Hambsch, Satoshi Kunieda, Wolf Mannhart, Benjaminas Marcinkevicius, Ronald Nelson, Gilles Noguere, Peter Schillebeeckx, Stanislav Simakov, Xi Tao, Andrej Trkov, Anton Wallner, Wenming Wang
Assessment of Novel Techniques for Nuclear Data Evaluation
Petter Helgesson, Denise Neudecker, Henrik Sjöstrand, Michael Grosskopf, Donald Smith, Roberto Capote
Predicting Spectrum Averaged Cross Sections in Prompt Fission Neutron Fields
Roberto Capote, Andrej Trkov
Rigorous Uncertainty Propagation Using a Dosimetry Transfer Calibration
Patrick Griffin, David Vehar, Edward Parma, Kelly Hahn
Evaluation of the 23Na(N,Gamma) Reaction Cross Section
Sergei Badikov, Konstantin Zolotarev
Retrospective Dosimetry Analysis of Top Support Plug Samples from Scrap Surveillance Capsule Material for Qualifying Calculations in the Extended Beltline Region of PWRS
Greg Fischer, Byoung Kim
Neutron Fluence Monitoring for Subsequent License Renewal
Amrit Patel, Joel Risner, Benjamin Parks, Matthew Hardgrove
Advanced Neutron Dosimetry on VVER-440 Aimed to Reactor Equipment Load Evaluation during Lifetime Prolongation
Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov, Jörg Konheiser, Alexander Dzhalandinov, Alexander Sidorov, Sergey Aleshin, Sergey Zaritskiy, Alexander Egorov, Vyacheslav Kochkin, Dmitry Erak, Pavel Panferov, Denis Makhotin
Vanadium Self-Powered Detector Gamma Response in Commercial Pressurized Water Reactor
Jianwei Chen
Supplemental Surveillance Capsule Application for Optimized Power Reactor, OPR1000, in Korea
YoungJae Maeng, MiJoung Lim, KyungSik Kim, ChoonSung Yoo, Byoung Kim
Radiation-Induced Degradation of Concrete in NPPs
Igor Remec, Thomas Rosseel, Kevin Field, Yann Le Pape
Validation of MCBEND Dosimetry Predictions against Measurements from Hunterston B Advanced Gas-Cooled Reactor
Dennis Allen, Dean Thornton, Simon Shaw, Jan Wagemans, Geoff Whiley, James Watson, Adrian Huggon, Paolo Mason
Surveillance Dosimetry at Sizewell B Nuclear Power Plant
Simon Shaw, Dean Thornton
Approaches for Estimation of Radiation Damage Parameters on VVER Equipment and Their Implementation during Monitoring Procedure
Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov
Enhancement of STAYSL_PNNL with IRDFF/V1.05 to 60 MeV
Lawrence Greenwood, Bruce Pierson, Christian Johnson
Numerical Experiment to Validate an Advanced Methodology for Dosimetry in French Nuclear Reactors
Nicolas Thiollay, Clément Fausser, Stéphane Bourganel, Pietro Mosca
The VENUS-F Reactor for Nuclear Data Validation
Antonín Krása, Peter Baeten, Luca Fiorito, Jan Heyse, Anatoly Kochetkov, Stefan Kopecky, Nadia Messaoudi, Carlos Paradela, Peter Schillebeeckx, Alexey Stankovskiy, Gert van den Eynde, Guido Vittiglio, Jan Wagemans
Analysis of the FLUOLE-2 Program: UOX/MOX Core Loading Configurations
Stéphane Bourganel, Nicolas Thiollay, Pietro Mosca
On the Influence of Biological Shielding on Neutron Flux behind Reactor Pressure Vessel
Michal Košt´ál, Vít Klupák, Vojtěch Rypar, Evžen Losa, František Cvachovec, Bohumil Jánský, Davit Harutunyan, Martin Schulc, Evžen Novák, Sergey Zaritskiy, Anais Bresson, Michel Tommy-Martin, Cecile-Aline Gosmain
Estimation of Void Swelling in VVER-1000 Baffle Using Benchmark in LR-0 Reactor
Davit Harutyunyan, Ihor Mirzov, Michal Košt´ál, Martin Schulc, Vít Klupák
Spectrum Adjustment Results for Three Environments in the ACRR Central Cavity Using a Genetic Algorithm
Richard Vega, Edward Parma
Design and Response Testing of Boron-Diffused Silicon Carbide Neutron Detectors for Dosimetry and Monitoring Applications
Krishna Mandal, Towhid Chowdhury, Cihan Oner, Frank Ruddy
Practical Considerations for Reactor Spectrum Characterization: Lessons Learned
Thomas Quirk, Edward Parma
Exploration of the 1 keV–1 MeV Neutron Energy Range Using Zirconium Dosimeters
Nicolas Thiollay, Victoria Sergeyeva, Abdallah Lyoussi, Christophe Domergue, Christophe Destouches
Simultaneous Measurements of Nuclear Heating and Thermal Neutron Flux Obtained with the CALMOS-2 Measurement Device inside the OSIRIS Reactor
Hubert Carcreff, Laurent Salmon, Valérie Lepeltier, Jean-Marie Guyot, Eric Bouard
New Evaluation of Neutron Fluence Measurements by Diamond Detectors
Vadim Nikolaenko, Sergey Zaritskiy, Alexander Egorov, Mikhail Saltykov, Ilya Bachuchin
Gamma-Ray Imaging System for Fukushima Daiichi Nuclear Power Plant using Silicon Strip Detector
Masaaki Kaburagi, Yuki Sato, Yuri Yoshihara, Kenji Shimazoe, Hiroyuki Takahashi, Tatsuo Torii
The Effects of Radiation Hardening on the Reusability of CaF2:Mn TLDs
Joshua Daniel, Dale Henneke, David Vehar
Image Reconstruction of Radioactive Contamination Due to the Fukushima-Daiichi Nuclear Power Station Accident Using a Compact Compton Camera
Yuki Sato, Yuta Terasaka, Hiroko Miyamura, Masaaki Kaburagi, Yuta Tanifuji, Kuniaki Kawabata, Tatsuo Torii
Evaluation of the Pool Critical Assembly Benchmark with Explicitly Modeled Geometry Using MCNP6’s Unstructured Mesh Capabilities
Joel Kulesza, Roger Martz
Deterministic Model of PWR Fast Fluence for Uncertainty Propagations with the Code APOLLO3®
Pietro Mosca, Laura Clouvel, Théophile Lacaze, Sébastien Lahaye, Jean Lautard, Anne Baudron
Derivation of Ex-Core Detector Response Functions for Sizewell B
Christophe Murphy, George Wright, Dean Thornton, Simon Shaw, Paul Bryce
High-Fidelity Gamma Transport Analysis for the Advanced Test Reactor Fuel Storage Canal
David Nigg, James Sterbentz
A Case Study into the Effect of Excess Reactivity on the Results of Dosimetry Calculations Performed with Fixed Source Codes
David Powney, George Wright, Dean Thornton, Simon Shaw, Paul Bryce
Using Total Monte Carlo to Calculate the Full Covariance Matrix of a Neutron Spectrum
Nicola Asquith, Steven van der Marck
Fast Neutron Flux and DPA Rates in NuScale SMR Core Components and Vessels
Wei Zhang, Mark Shaver, Ruwan Ratnayake, Kent Welter
Comparative Study of Fast Neutron Fluence between RAPTOR-M3G and TORT for Commercial Pressurized Water Reactor Vessel Extended Beltline
Jianwei Chen, Greg Fischer
Tritium Management in FLiBe-cooled Reactors: Assessing All Pathways of Tritium Production in a Detailed Model
Timothy Flaspoehler, Bojan Petrovic
Experimental and Computational Validation of RAPID
Nathan Roskoff, Alireza Haghighat, Valerio Mascolino
Methodology Qualification for the 3D RAPTOR-M3G Discrete Ordinates Transport Code on Traditional Beltline
Jianwei Chen, Greg Fischer, Byoung Kim
Monte Carlo Calculation Procedure and Its Implementation for Radiation Load Estimation on Russian VVER Reactor Equipment
Silvio Baier, Jörg Konheiser, Pavel Borodkin, Azamat Gazetdinov, Nikolay Khrennikov
Co-60 Filter Box Optimization
K. DePriest, David Vehar, Thomas Laub
Study of Epithermal-Neutron Spectrum Variation versus Depth in Water Phantoms
Grazia Gambarini, Daniela Bettega, Andrea Gebbia, Emanuele Artuso, Marco Felisi, Dario Giove, Elisabetta Durisi, Valeria Monti, Vit Klupák, Ladislav Viererbl, Miroslav Vins
Committee: E10
DOI: 10.1520/STP1608-EB
ISBN-EB: 978-0-8031-7662-1
ISBN-13: 978-0-8031-7661-4