Reactor Dosimetry: 14th International Symposium

STP Published: 2012

STP1550-EB

Reactor Dosimetry: 14th International Symposium

Editor(s): D.W. Vehar

Fifty-seven peer-reviewed papers provide an extensive examination of timely topics in the field of Reactor Dosimetry. Also, two keynote papers address: the energy future and structural materials for innovative nuclear systems.

Topics cover:
• Reactor surveillance and plant life
• Nuclear data, uncertainties, and sensitivity studies
• Reactor surveillance and retrospective dosimetry
• Benchmarks and intercomparisons
• Research/test reactor and accelerator dosimetry
• Neutron and gamma-ray transport calculations and modelling
• Experimental techniques, new developments, and optical methods

Reactor Dosimetry and RPV Life Management

S. Belousov, K. Ilieva, M. Mitev

Korean Standard Nuclear Plant Ex-Vessel Neutron Dosimetry Program Ulchin 4

J. I. Duo, J. Chen, J. A. Kulesza, A. H. Fero, C. S. Yoo, B. C. Kim

Dosimetry Assessments for the Reactor Pressure Vessel and Core Barrel in UK Pressurized Water Reactor (PWR) Plant

D. A. Thornton, D. A. Allen, A. P. Huggon, D. J. Picton, A. T. Robinson, R. J. Steadman, T. Serén, M. Lipponen, T. Kekki

Comparison of Attenuation Coefficients for VVER-440 and VVER-1000 Pressure Vessels

Milan Marek, Jan Rataj, Stanislav Vandlik

Ringhals Unit 3 and 4—Fluence Determination in a Historic and Future Perspective

Eva-Lena Green, Jenny Roudén, Pål Efsing

Dosimetry Analyses of the Ringhals 3 and 4 Reactor Pressure Vessels

Joel A. Kulesza, Arnold H. Fero, Jenny Roudén, Eva-Lena Green

Modernization of Existing VVER-1000 Surveillance Programs

V. Kochkin, D. Erak, D. Makhotin

Exposure Conditions of Reactor Internals of Rovno VVER-440 Nuclear Power Plant Units 1 and 2

O. V. Grytsenko, S. M. Pugach, V. L. Diemokhin, V. N. Bukanov, M. Marek, S. Vandlik

2010 Review of Neutron and Non-Neutron Nuclear Data

N. E. Holden

Path Forward for Dosimetry Cross Sections

P. J. Griffin, C. D. Peters

A New Technique for Dosimetry Reaction Cross-Section Evaluation

S. A. Badikov

New Work on Updating and Extending the Nuclear Data Standards

A. D. Carlson, V. G. Pronyaev, R. Capote, F. -J. Hambsch, F. Käppeler, C. Lederer, W. Mannhart, A. Mengoni, R. O. Nelson, P. Schillebeeckx, P. Talou, S. Tagesen, H. Vonach, A. Vorobyev, A. Wallner

Uncertainties of Responses Calculated with a “Tuned” Library: Geometrical and Algebraic Insights

R. L. Perel

A New Formulation of the Unified Monte Carlo Approach (UMC-B) and Cross-Section Evaluation for the Dosimetry Reaction ⁵⁵Mn(n,γ)⁵⁶Mn

Roberto Capote, Donald L. Smith, Andrej Trkov, Mehdi Meghzifene

Updating and Extending the IRDF-2002 Dosimetry Library

Roberto Capote, Konstantin I. Zolotarev, Vladimir G. Pronyaev, Andrej Trkov

Uncertainty-Accounted Calculational–Experimental Approach for Improved Conservative Evaluations of VVER RPV Radiation Loading Parameters

P. G. Borodkin, G. I. Borodkin, N. N. Khrennikov

Sensitivity of Adjustment to Parameter Correlations and to Response-Parameter Correlations

J. J. Wagschal

Application of Different Nuclides in Retrospective Dosimetry

J. Konheiser, S. Mittag, H. -W. Viehrig, B. Gleisberg

Retrospective Dosimetry Analyses of Reactor Vessel Cladding Samples

L. R. Greenwood, C. Z. Soderquist, A. H. Fero

Neutron Flux Reduction Programs for Reactor Pressure Vessel of Korea Nuclear Unit 1

Choon Sung Yoo, Byoung Chul Kim

A Three-Dimensional Methodology for the Assessment of Neutron Damage and Nuclear Energy Deposition in Graphite Components of Advanced Gas-Cooled Reactors

D. O. Morgan, A. T. Robinson, D. A. Allen, D. J. Picton, D. A. Thornton, S. E. Shaw

Dosimetry of the Decommissioned High-Flux Beam Reactor at Brookhaven Lab

J. -P. Hu, R. N. Reciniello, N. E. Holden

The Current Status of the Shielding Integral Benchmark Archive and Database (SINBAD)

B. L. Kirk, R. E. Grove, I. Kodeli, J. Gulliford, E. Sartori

VENUS-F: A First Fast Lead Critical Core for Benchmarking

A. Kochetkov, J. Wagemans, G. Vittiglio

Benchmarking of Neutron Production of Heavy-Ion Transport Codes

I. Remec, R. M. Ronningen, L. Heilbronn

Neutron and Gamma Field Investigations in the VVER-1000 Mock-Up Concrete Shielding on the Reactor LR-0

S. Zaritsky, A. Egorov, B. Ošmera, M. Mařik, V. Rypar, F. Cvachovec, A. Kolros

New Measurements and the Associated Unfolding Methodologies to Characterize the Caliban Pulsed Reactor Cavity Neutron Spectrum by the Foil Activation Method

X. Jacquet, P. Casoli, N. Authier, G. Rousseau, C. Barsu

Los Alamos National Laboratory Fission Basis

A. L. Keksis, M. B. Chadwick, H. D. Selby, M. R. Mac Innes, D. W. Barr, R. A. Meade, C. J. Burns, T. C. Wallstrom

Sensitivity Studies Associated with Dosimetry Experiment Interpretation

S. Bourganel, M. Soldevila, A. Ferrer, G. Grégoire, C. Destouches, D. Beretz

Comparison of Regulatory Guide 1.99 Fluence Attenuation Methods

Eric N. Jones

The Power Distribution and Neutron Fluence Measurements and Calculations in the VVER-1000 Mock-Up on the LR-0 Research Reactor

M. Košt'ál, V. Juříček, V. Rypar, M. Švadlenková, F. Cvachovec

VVER-440 and VVER-1000 Reactor Dosimetry Benchmark—BUGLE-96 Versus ALPAN VII.0

J. I. Duo

Development and Experimental Validatio of a Calculation Scheme for Nuclear Heating Evaluation in the Core of the OSIRIS Material Testing Reactor

F. Malouch

Analysis of Gamma-Ray Dosimetry Experiments in the Zero Power MINERVE Facility

H. Amharrak, J. Di Salvo, A. Lyoussi, A. Roche, M. Masson-Fauchier, J. C. Bosq, M. Carette

Jules Horowitz Reactor, a New Irradiation Facility: Improving Dosimetry for the Future of Nuclear Experimentation

Gilles Grégoire, Daniel Beretz, Christophe Destouches

Measurements of Actinide-Fission Product Yields in Caliban and Prospero Metallic Core Reactor Fission-Neutron Fields

P. Casoli, N. Authier, J. Laurec, E. Bauge, T. Granier

Reactor Pulse-Repeatability Studies at the Annular Core Research Reactor

K. Russell DePriest, Tri Q. Trinh, S. Michael Luker

A Feasibility Study to Determine Cooling Time and Burnup of Advanced Test Reactor Fuel Using a Nondestructive Technique and Three Types of Gamma-ray Detectors

J. Navarro, R. Aryaeinejad, D. W. Nigg

The Neutron Standard Fields at the BR1 Reactor at SCK•CEN

J. Wagemans, E. Malambu, L. Borms

Photon Spectrum behind Biological Shielding of the LVR-15 Research Reactor

V. Klupák, L. Viererbl, Z. Lahodová, M. Marek, M. Vinš

Ex-Vessel Neutron Dosimetry Analysis for Westinghouse 4-Loop XL Pressurized Water Reactor Plant Using 3D Parallel Discrete Ordinates Code RAPTOR-M3G

J. Chen, F. A. Alpan, G. A. Fischer, A. H. Fero

A Broad-Group Cross-Section Library Based on ENDF/B-VII.0 for Fast Neutron Dosimetry Using the CPXSD Methodology

F. A. Alpan

Development and Testing of the VITAMIN-B7/BUGLE-B7 Coupled Neutron-Gamma Multigroup Cross-Section Libraries

J. M. Risner, D. Wiarda, T. M. Miller, D. E. Peplow, B. W. Patton, M. E. Dunn, B. T. Parks

Application of Ex-Vessel Neutron Dosimetry Combined with In-core Measurements for Correction of Neutron Source Used for Reactor Pressure Vessel Fluence Calculations

P. G. Borodkin, G. I. Borodkin, N. N. Khrennikov, J. Konheiser

Neutron Flux Measurements in the Side-Core Region of Hunterston B Advanced Gas-Cooled Reactor

D. A. Allen, S. E. Shaw, A. P. Huggon, R. J. Steadman, D. A. Thornton, G. S. Whiley

Analysis of Dosimetry from the H. B. Robinson Unit 2 Pressure Vessel Benchmark Using RAPTOR-M3G and ALPAN

Greg A. Fischer

The Fast Neutron Fluence and the Activation Detector Activity Calculations Using the Effective Source Method and the Adjoint Function

J. Hep, A. Konečná, V. Krýsl, V. Smutný

A Database-Informed Approach to New Plant Shielding Design

Timothy M. Lloyd

EPR/PTFE Dosimetry for Test Reactor Environments

D. W. Vehar, P. J. Griffin, T. J. Quirk

CALMOS: Innovative Device for the Measurement of Nuclear Heating in Material Testing Reactors

H. Carcreff

Fitting Method for Spectrum Deduction in High-Energy Neutron Field Induced by GeV-Protons Using Experimental Reaction-Rate Data

Y. Kasugai, N. Matsuda, Y. Sakamoto, H. Nakashima, H. Yashima, H. Matsumura, H. Iwase, H. Hirayama, N. Mokhov, A. Leveling, D. Boehnlein, K. Vaziri, G. Lauten, K. Oishi, T. Nakamura

Development of INSPCT-S for Inspection of Spent Fuel Pool

William Walters, Alireza Haghighat, Shivakumar Sitaraman, Young Ham

Design and Testing of a Boron Carbide Capsule for Spectral Tailoring in Mixed-Spectrum Reactors

L. R. Greenwood, R. Wittman, B. P. Pierson, L. A. Metz, R. Payne, E. C. Finn, J. I. Friese

An Alternative Calibration Method for Counting P-32 Reactor Monitors

T. J. Quirk, D. W. Vehar

New Experimental Proposal for ²³⁵U PFNS Measurement to Answer a Fifty Year Old Question

N. Kornilov, T. Massey, S. Grimes, A. Voinov

Development of Neutron Measurement in Intense Gamma Field Using New Type of Nuclear Emulsion

J. Kawarabayashi, K. Ishihara, K. Takagi, H. Tomita, T. Iguchi, T. Naka, K. Morishima, S. Maeda

Development of an Active Detector for the Characterization of the Late-Time Radiation Environment from a Reactor Pulse

S. M. Luker, P. J. Griffin, N. R. Kolb, G. N. Naranjo, A. J. Suo-Anttila

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Details

Developed by Committee: E10

Pages: 724

DOI: 10.1520/STP1550-EB

ISBN-EB: 978-0-8031-7553-2

ISBN-13: 978-0-8031-7536-5