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EPJ Web of Conferences

Volume 308 (2024)

ISRD 17 – International Symposium on Reactor Dosimetry (Part II)

Lausanne, Switzerland, May 21-26, 2023
P. Frajtag, D. Thornton and J. Wagemans (Eds.)

ISBN: 978-2-7598-9127-6

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About the conference

Published online: 11 November 2024

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Open Access

Statement of Peer review

Published online: 11 November 2024

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ISRD 17 (Part I)

Experimental Techniques, Measurements and Monitoring

Open Access

Transmutation detectors for fast neutron fluence measurements 01005

Alena Krechlerová, Ladislav Viererbl, Jan Lorinčík, Ivan Elantyev, Hana Assmann Vratislavská, Vít Klupák and David Harut

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801005

Open Access

On the effect of the core boundary power distribution on the radiation situation in reactor components 01006

Michal Košťál, Vít Klupák, Zdeněk Matěj, Filip Mravec, František Cvachovec, Vojtěch Rypar, Evžen Losa, David Harut, Martin Schulc, Bohumil Jánský et al. (5 more)

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801006

Open Access

Recent improvements in X-ray spectrometry measurements performed at the MADERE facility dedicated to reactor dosimetry requirements 01007

David Tisseur, Christophe Domergue, Christophe Destouches, Hervé Philibert, Alexandra Pepino, Jonathan Bonora, Nicolas Thiollay, Marie Christine Lépy, Jonathan Riffaud and Víctor Hernández-Elvira

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801007

Open Access

Alternatives to NIST Cf-252 Iirradiations for Transfer Calibration of S-32 Neutron Monitors 01008

David Vehar, William Charlton and Mark Andrews

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801008

Open Access

Extending the panel of inelastic scattering reactions availaible for dosimetry: Definition of the experimental campaign at the JSI TRIGA reactor 01009

Gilles Grégoire, Vladimir Radulovic, Gasper Žerovnic, Christophe Domergue, Hervé Philibert, Clément Fausser, David Tisseur, Nicolas Thiollay, Loic Barbot and Christophe Destouches

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801009

Open Access

Perovskite-based detector for reactor dosimetry monitoring 01010

Pavao Andricevic, Pavel Frajtag, Peter Szirmai, Gábor Náfrádi, Márton Kollár, László Forró, Endre Horváth and Andreas Pautz

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801010

Open Access

Mutual shielding of neutron activation foils 01011

Ernst Ippel, Adri Paardekooper, Bert Metz and Gregor Bolderink

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430801011

Calculational Methods

Open Access

An automated weight window generator based on the recursive Monte-Carlo method for use in MC shielding calculations 02004

Pratibha Yadav, Silvio Baier, Jörg Konheiser and Reuven Rachamin

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802004

Open Access

Further development, validation and verification of the Monte-Carlo code TRAMO on ex-vessel experiments of the Greifswald NPP 02005

Silvio Baier, Jörg Konheiser and Erik Pönitz

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802005

Open Access

Reanalysis of graphite nuclear data limits for AGR dosimetry with updated carbon scattering data and Magnox plant measurements 02006

S.E. Shaw and D.A. Allen

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802006

Open Access

The fast neutron fluence and the activation monitor activity calculations using fine multigroup and continuous nuclear data 02007

Martin Lovecký, Pavlína Tušlová and Vladimír Smutný

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802007

Open Access

A flexible methodology for generating 3D graphite dosimetry data in Advanced Gas-Cooled Reactors 02008

Dennis Allen, Dean Thornton, James Watson and Simon Shaw

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802008

Open Access

Molten Salt Research Reactor (MSRR) shielding analysis using SCALE/MAVRIC sequence with continuous energy and multigroup cross sections 02009

Bojan Petrovic, Rakim Hirji and Kyle Carberry

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430802009

Reactor Surveillance, Plant Life Management and Decommissioning

Open Access

Improved determination of fast neutron fluence onto the WWER pressure vessel metal surveillance specimens 03002

O.M. Pugach, V.M. Bukanov, V.L. Diemokhin, O.V. Grytsenko and O.G. Vasylieva

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803002

Open Access

Four decades of progress in PWRs surveillance program dosimetry measurements at the MADERE platform 03003

Clément Fausser, Christophe Domergue, Hervé Philibert, Jonathan Bonora, Alexandra Pépino, Stéphane Bourganel, Kévin Jeuland, Céline Galant, Alexandre Subercaze, Gilles Grégoire et al. (3 more)

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803003

Open Access

A quantified approach to assessing the effectiveness of nuclear reactor pressure vessel neutron fluence monitoring programs 03004

Joel Kulesza and Greg Fischer

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803004

Open Access

Activity measurements and calculations for gamma-emitting radionuclides in concrete drill cores of unit 2 of the Greifswald NPP 03005

Erik Poenitz, Quirina Isabella Roode-Gutzmer, Astrid Barkleit and Joerg Konheiser

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803005

Open Access

Estimation of neutron fluence distribution within German PWR components for decommissioning studies 03006

Reuven Rachamin, Astrid Barkleit, Jörg Konheiser and Marcus Seidl

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803006

Open Access

Ex-core neutron exposure monitoring and reactor internals aging management at Ringhals 03007

Greg Fischer, Jenny Roudén, Johan Blomström and Sylena Smith

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803007

Open Access

DPA calculation in a stainless steel baffle of Chooz-A PWR using auto-dosimetry measurements 03008

Stéphane Bourganel, Antonio Galia, Jérémy Hure, Rémy Bonzom, Christophe Domain and Cécile-Aline Gosmain

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803008

Open Access

Investigation of RPV samples of the Greifswald NPP with focus on retrospective dosimetry 03009

Erik Poenitz and Joerg Konheiser

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803009

Open Access

The reactor pressure vessel surveillance program of the Belgian nuclear power plants 03010

Jan Wagemans and Nicolas Slosse

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803010

Open Access

Revision of PSI calculation capabilities and validation experience on the BEPU-type reactor dosimetry applications 03011

Alexander Vasiliev, Hakim Ferroukhi, Marko Pecchia, Dimitri Rochman, Axel Laureau, Vincent Lamirand and Andreas Pautz

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803011

Open Access

Westinghouse fluence methodology uncertainty estimates for reactor vessel internals fast neutron exposure evaluation in subsequent license renewal period 03012

Jianwei Chen, Benjamin Amiri and Jared Geer

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803012

Open Access

Ex-vessel neutron dosimetry results in the extended beltline region 03013

Eugene T. Hayes

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803013

Open Access

Results of the reactor dosimetry experiments performed for verification of the neutron transport calculations at the Hungarian Paks Nuclear Power Plant 03014

Eva M. Zsolnay, Szabolcs Czifrus, Dániel Kis, András Horváth and Anita Gerényi

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803014

Open Access

Secondary source reconfiguration for a Westinghouse four-loop plant 03015

Benjamin Amiri and Jianwei Chen

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430803015

Nuclear Data, Uncertainties and Adjustment

Open Access

Development and testing of WEASEL for least-squares neutron spectrum adjustment 04001

Greg Fischer

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430804001

Open Access

Measurements of ²³⁵U(nth,f) Spectrum Averaged Cross Sections (SACS) in zero power reactors 04002

Michal Košťál, Evžen Losa, Tomáš Czakoj, Tomáš Bílý, Martin Schulc, Vlastimil Juříček, Jan Šimon, Martin Mareček, Jan Uhlíř, Alena Krechlerová et al. (3 more)

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430804002

Open Access

Application of research reactor environments for validation of the IRDFF-II dosimetry cross section library 04003

Patrick Griffin, Curtis Peters, Edward Parma and David Vehar

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430804003

Open Access

Comparison of transport cross-section data generated with BONAMI and TRANSX 04004

Greg Fischer

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430804004

Dosimetry in Test and Research Reactors

Open Access

Godiva-IV dosimetry exercise 2022 preliminary results 06001

Aaron S. Tamashiro, Daniel K. Stone, Logan Anspach, Brian Champine, Mike Firpo, Sophia Uchiyama, Paige Witter, Paul Yap-Chiongco, Scarlett Mitchell, Catherine Percher et al. (35 more)

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806001

Open Access

On radiation situation in vicinity of PET production cyclotron 06002

Marek Zmeškal, Michal Košt’ál, Tomáš Czakoj, Jan Šimon, Martin Schulc, Šimon Vadják, Michal Antoš and Zdeněk Matěj

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806002

Open Access

A neutron fluence map of the Los Alamos National Laboratory Godiva IV critical assembly 06003

Jesse M. Roebuck, Danielle R. Redhouse, Joetta M. Goda, Melissa Moreno and Curtis Peters

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806003

Open Access

Fast and thermal neutron spectrum dosimetry measurements in the Advanced Test Reactor large-B and small-l positions following the sixth core internals change-out 06004

Michael Reichenberger, Andrew Maile, Matthew Johnson, Daren Norman, Samuel Bays, Kelly McCary and Nathan Manwaring

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806004

Open Access

Godiva IV central cavity neutron environment characterization with threshold neutron detectors 06005

Nicholas Whitman, Bruce Pierson, Robert Weldon, Theresa Cutler, Matthew Gooden, Jesson Hutchinson, Rene Sanchez, Travis Grove and Joetta Goda

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806005

Open Access

Application of reactor dosimetry techniques for source term validation in F-18 production with a medical cyclotron 06006

Joerg Konheiser and Stefan E. Mueller

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806006

Open Access

Radiation characterization summary of the NETL beam port 1/5 free-field environment at the 128-inch core centerline adjacent location 06007

Danielle Redhouse, William Charlton, Edward Parma, Curtis Peters, Mark Andrews, Jesse Roebuck and Ryan Mulcahy

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806007

Open Access

Radiation characterization summary for the WSMR fast burst reactor environment at the 6-inch location 06008

Danielle Redhouse, Edward S. Lum, Johnathon Koglin, Edward J. Parma, Curtis D. Peters, Mikhail Finko, Jesse M. Roebuck, David W. Vehar, Frank Sage, Andrew M. Tonigan et al. (6 more)

Published online: 11 November 2024

DOI: 10.1051/epjconf/202430806008

EPJ

EPJ Web of Conferences

Volume 308 (2024)

ISRD 17 – International Symposium on Reactor Dosimetry (Part II)

About the conference

Statement of Peer review

ISRD 17 (Part I)

Experimental Techniques, Measurements and Monitoring

Transmutation detectors for fast neutron fluence measurements 01005

On the effect of the core boundary power distribution on the radiation situation in reactor components 01006

Recent improvements in X-ray spectrometry measurements performed at the MADERE facility dedicated to reactor dosimetry requirements 01007

Alternatives to NIST Cf-252 Iirradiations for Transfer Calibration of S-32 Neutron Monitors 01008

Extending the panel of inelastic scattering reactions availaible for dosimetry: Definition of the experimental campaign at the JSI TRIGA reactor 01009

Perovskite-based detector for reactor dosimetry monitoring 01010

Mutual shielding of neutron activation foils 01011

Calculational Methods

An automated weight window generator based on the recursive Monte-Carlo method for use in MC shielding calculations 02004

Further development, validation and verification of the Monte-Carlo code TRAMO on ex-vessel experiments of the Greifswald NPP 02005

Reanalysis of graphite nuclear data limits for AGR dosimetry with updated carbon scattering data and Magnox plant measurements 02006

The fast neutron fluence and the activation monitor activity calculations using fine multigroup and continuous nuclear data 02007

A flexible methodology for generating 3D graphite dosimetry data in Advanced Gas-Cooled Reactors 02008

Molten Salt Research Reactor (MSRR) shielding analysis using SCALE/MAVRIC sequence with continuous energy and multigroup cross sections 02009

Reactor Surveillance, Plant Life Management and Decommissioning

Improved determination of fast neutron fluence onto the WWER pressure vessel metal surveillance specimens 03002

Four decades of progress in PWRs surveillance program dosimetry measurements at the MADERE platform 03003

A quantified approach to assessing the effectiveness of nuclear reactor pressure vessel neutron fluence monitoring programs 03004

Activity measurements and calculations for gamma-emitting radionuclides in concrete drill cores of unit 2 of the Greifswald NPP 03005

Estimation of neutron fluence distribution within German PWR components for decommissioning studies 03006

Ex-core neutron exposure monitoring and reactor internals aging management at Ringhals 03007

DPA calculation in a stainless steel baffle of Chooz-A PWR using auto-dosimetry measurements 03008

Investigation of RPV samples of the Greifswald NPP with focus on retrospective dosimetry 03009

The reactor pressure vessel surveillance program of the Belgian nuclear power plants 03010

Revision of PSI calculation capabilities and validation experience on the BEPU-type reactor dosimetry applications 03011

Westinghouse fluence methodology uncertainty estimates for reactor vessel internals fast neutron exposure evaluation in subsequent license renewal period 03012

Ex-vessel neutron dosimetry results in the extended beltline region 03013

Results of the reactor dosimetry experiments performed for verification of the neutron transport calculations at the Hungarian Paks Nuclear Power Plant 03014

Secondary source reconfiguration for a Westinghouse four-loop plant 03015

Nuclear Data, Uncertainties and Adjustment

Development and testing of WEASEL for least-squares neutron spectrum adjustment 04001

Measurements of 235U(nth,f) Spectrum Averaged Cross Sections (SACS) in zero power reactors 04002

Application of research reactor environments for validation of the IRDFF-II dosimetry cross section library 04003

Comparison of transport cross-section data generated with BONAMI and TRANSX 04004

Dosimetry in Test and Research Reactors

Godiva-IV dosimetry exercise 2022 preliminary results 06001

On radiation situation in vicinity of PET production cyclotron 06002

A neutron fluence map of the Los Alamos National Laboratory Godiva IV critical assembly 06003

Fast and thermal neutron spectrum dosimetry measurements in the Advanced Test Reactor large-B and small-l positions following the sixth core internals change-out 06004

Godiva IV central cavity neutron environment characterization with threshold neutron detectors 06005

Application of reactor dosimetry techniques for source term validation in F-18 production with a medical cyclotron 06006

Radiation characterization summary of the NETL beam port 1/5 free-field environment at the 128-inch core centerline adjacent location 06007

Radiation characterization summary for the WSMR fast burst reactor environment at the 6-inch location 06008

Conference announcements

Measurements of ²³⁵U(nth,f) Spectrum Averaged Cross Sections (SACS) in zero power reactors 04002