|
|
|
Digital Library / STP / STP1398-EB
 |
STP1398
Reactor Dosimetry: Radiation Metrology and Assessment
Williams JG, Vehar DW, Ruddy FH, Gilliam DM
Pages: 856
Published: 2001
Format: PDF (17M)
Price: $273 [Download Now]
Other books in this series
|
|
One hundred papers provide an extensive overview of latest advances in reactor dosimetry. An additional nine summaries provide the status of technical workshops held at the Tenth International Symposium on Reactor Dosimetry and three keynote papers address: why we need dosimetry; the role of ASTM Committee E10 on Nuclear Technology, and reactor dosimetry activities in Japan. The 100 papers span seven areas including: Power Reactor Surveillance includes 17 papers on reactor vessel surveillance for pressurized water reactors (PWRs) in France, United Kingdom, Korea, Japan and the United States; for VVERs in Russia, Czech Republic, Ukraine, Bulgaria and Hungry; for heavy water reactor in Argentina; and for MAGNOX reactors in the United Kingdom. Three papers also address concrete structures outside reactor vessels Test Reactors and Accelerator Sources addresses facilities for such applications as boron neutron capture therapy (BNCT), semiconductor testing, structural steel testing, and nuclear fuel testing in a variety of types of reactor and accelerator neutron sources. Benchmarks and Intercomparisons contains 11 papers on experiments and analysis used to test and improve techniques and data by means of standards and calibrations and specially designed reference fields. Cross Sections and Nuclear Data provides 11 papers on cross section measurements and evaluations; and compilation and testing of cross section libraries. Calculations and Adjustment Methods includes 14 articles, half on neutron transport codes for modeling LWR vessels and internal structures. Remaining papers address computational methods for estimation of induced activity in ex-vessel components and neutron spectrum adjustment methods. Damage Correlations and Damage Dosimetry discusses calculation of displacements-per-atom, kerma, and atomic-recoil energy spectra, and data libraries derived for these. Experimental Techniques are discussed in 21 papers. Half address active detector techniques, including spectrometers and instruments for in-core monitoring and the remaining discuss passive irradiation monitoring, including activation monitoring methods.
Table of Contents
Why Do We Need Dosimetry?
Gérard R., Zaritsky S.
ASTM Standards for Reactor Dosimetry and Pressure Vessel Surveillance
Griffin P.
Developments in Reactor Dosimetry in Japan
Kimura I.
French PWR Vessel Surveillance Program Dosimetry: Experience Feedback from More than a Hundred Capsules
Beretz D., Brillaud C., Destouches C., Saillet S.
Reactor Pressure Vessel Neutron Dosimetry Assessments for UK PWR Plant
Thornton D., Lewis T., Mossop J., Page C., Haddock S.
Assessment of Neutron Fluence Uncertainty and its Impact on Safety Issues
Lippincott E.
Review of Problems and Requirements in VVER Reactor-Type Pressure Vessel Dosimetry
Zaritsky S., Platonov P., Nikolaev Y., Ošmera B., Valenta V.
Overview of the Surveillance Dosimetry Activities in Ukraine
Bukanov V., Dyemokhin V., Gavriljuk V., Grytsenko O., Nedyelin O., Vasylyeva E.
Improved Evaluation of the Atucha-I Ex-Vessel Dosimetry
Albornoz A., Blaumann H., Lopasso E., Blanco A., Gennuso G., Serra O.
Reactor Dosimetry in the Surveillance Program of Kozloduy NPP Reactor Pressure Vessels
Ilieva K., Belousov S., Apostolov T., Monev M.
Evaluation of the Reactor Dosimetry Results Obtained During the First Ten Years of the RPV Surveillance Program at the NPP Paks
Zsolnay &., Szondi E., Oszvald F.
Neutron Dosimetry for VVER Reactor Pressure Vessels in the Czech Republic
Brumovsky M., Erben O., Hogel J., Osmera B.
Analysis of Pressure Vessel Surveillance Dosimetry Inserted into Korean PWR
Gil C., Kim J., Chang J.
Integrity Assessment for Aging Reactor Vessel of Japan's First Generation PWR Plants
Sato T., Kusuki A., Shiota S.
Measurement of Neutron Flux Distribution for Decommissioning in Tokai Power Station
Shirakawa M., Yamamoto T., Nakazawa M.
Impact of the ENDF/B-VI Cross Sections on the RPV Fluence Determination
Remec I.
Factors Affecting Predicted Neutron Dose Rates to Steel Pressure Vessels of Magnox Plant
Thornton D.
The Attenuation of Neutron Dose Rates through the Steel Pressure Vessels of Magnox Power Plants
Fletcher A., Mossop J., Page C.
Assessment of Activation of Concrete Wall for Decommissioning of Nuclear Power Plants
Matsumura T., Hattori T., Kawabe T.
Use of SSTRs and a Multi-Component Shield Assembly to Measure Radiation Penetrating the Reactor Biological Shield in the Presence of Radiation Streaming from Other Sources
Fero A.
Spectral Unfolding of Mixed Proton/Neutron Fluences in the LANSCE Irradiation Environment
James M., Maloy S., Sommer W., Ferguson P., Fowler M., Mueller G., Corzine R.
Neutron Beam Characterization at the Finnish BNCT Facility — Measurements and Calculations
Serén T., Auterinen I., Kotiluoto P., Seppälä T.
Establishment of Fe-Filtered Neutron Beam Facility and Measurement of the Filtered Neutrons
Kobayashi K., Yoshimoto T., Fujita Y., Utsuro M., Utsumi H.
Design and Characterization of a Facility for Fast Neutron Irradiation of Semiconductors at Penn State
Petrovic B., Abou-Zaid A., Haghighat A., Daubenspeck T.
Comprehensive Nuclear Fuel Dosimetry Program in the OSIRIS Reactor
Alberman A., Morin C., Marchand L., Marcault A.
Dosimetry of a GeV Proton-Driven Spallation Neutron Field by the Activation Method
Kasugai Y., Takada H., Ikeda Y.
The Irradiation Characteristics of the KUR Heavy Water Facility — Neutron Energy Spectra for Several Irradiation Modes
Kobayashi T., Sakurai Y., Kobayashi K.
Radiation Dosimetry at the BNL High Flux Beam Reactor and Medical Research Reactor
Holden N., Hu J., Greenberg D., Reciniello R., Farrell K., Greenwood L.
Measurement of Neutron Spectrum at HANARO
Hong U., Kang H., Seo C., Kang Y.
Combining Measurements and 3D Neutron Transport Calculations — A Powerful Tool in Detailed Neutron Dosimetry and Damage Analysis
Voorbraak W., Freudenreich W., Ketema D.
Characterization of Neutron Field for Stainless Steel Irradiation Experiments in JMTR
Shimakawa S., Nagao Y., Fujiki K.
Assessment of the Fission Power Level in Fuel Rods Irradiated in the High Flux Materials Testing Reactor BR2 with the Aid of Fluence Dosimetry and Comparison with Other Methods
De Raedt C., Malambu E., Bodart S., Wéber M., Willekens M.
Local Change of a Neutron Spectrum in the Fast Reactor BOR-60 for Extension of Research Tasks
Tellin A., Shimansky G., Yakovleva I.
Improvement of Reactor Dosimetry for Irradiation Tests in the Experimental Fast Reactor JOYO
Sekine T., Aoyama T., Yoshida A., Suzuki S.
Estimation of Low Level Neutron Doses Based on Neutron Spectra in the Vicinity of a Nuclear Reactor
Urabe I., Sagawa H., Ogawa Y., Ohsawa T., Kobayashi K., Yoshimoto T., Tsujimoto T.
Conceptual Neutronics Design of “Neutron Factory” as a Future Plan on Neutron Source in Kyoto University Research Reactor Institute (KURRI)
Shiroya S., Unesaki H., Kawase Y., Moriyama H., Inoue M.
Results from the NIST Round Robin Test of Fissionable Dosimeters in a Reactor Leakage Spectrum
Adams J.
New NEA Benchmarks for Calculating Fast Neutron Fluence in the Reactor Pressure Vessel
Hehn G., Na B.
Database for WWER-1000 Reactor Pressure Vessel IAEA Regional Project RER 4/017
Ošmera B., Lyssakov V., Cvachovec F., Hudec F., Janský B., Mikuš J., Novák E., Pošta S., Turzík Z., Hort M., Krysl V., Smutný V., Zaritsky S., Alekseev N., Gurevitch M., Egorov A., Brodkin E., Ilieva K., Belousov S., Kovbasensko J., Uritani A., Misawa T., Mori C.
Balakovo-3 Ex-vessel Exercise: Intercomparison of Results
Borodkin G., Kovalevich O., Barz H., Böhmer B., Stephan I., Ait Abderrahim H., Voorbraak W., Hogel J., Polke E., Schweighofer W., Seren T., Borodin A., Vikhrov V., Lichadeev V., Markina N., Grigoriev E., Troshin V., Penev I., Kinova L.
Re-analysis of the Experimental Leakage Neutron Spectrum from a Silicon Spherical Shell with Incident 14 MeV Neutrons using Different and Modified Neutron Cross Section Libraries
Ichihara C., Hayashi S., Kimura I., Yamamoto J., Takahashi A.
Monte Carlo Calculations of Neutron Fluence Spectra, Activation Measurements, Uncertainty Analysis and Spectrum Adjustment for the KORPUS Dosimetry Benchmark
Barz H., Boehmer B., Konheiser J., Stephan I.
Actual and Potential Measurements of Fission-Rate Ratios in the NIST Iron Sphere
Perel R., Wagschal J., Yeivin Y.
Adjustment of the 235U Fission Spectrum
Griffin P., Williams J.
Analysis of the ORNL PCA Benchmark Using TORT and BUGLE-96
Fero A., Anderson S., Roberts G.
Development of Calibration Fields of Intermediate Neutrons by Using Several Sources
Takeda N., Kudo K., Fujishiro M., Okamoto K., Kobayashi K., Yoshimoto T.
A Study on 14 MeV Neutron Beam Characteristics and its Applications
Sakane H., Uno Y., Maekawa F., Kasugai Y., Konno C., Kaneko J., Ikeda Y.
Integral Assessment of the Revised JENDL Dosimetry File
Kobayashi K., Iguchi T., Iwasaki S., Aoyama T., Shimakawa S., Ikeda Y., Odano N., Sakurai K., Shibata K., Nakagawa T., Nakazawa M.
High Energy Neutron Activation Cross Sections
Nakamura T., Kim E., Uwamino Y., Nakao N., Tanaka S.
SPALLDOS: New Neutron Metrology Cross-Section Library for Use at Spallation Neutron Sources
Szondi E., Zsolnay &., Hegedüs F., Tobler L.
Integral Testing of Spallation Cross Sections for Neutron Dosimetry at 113 and 256 MeV
Greenwood L.
Production of a Dosimetry Cross Section Set Up to 50 MeV
Maekawa F., von Möllendorff U., Wilson P., Wada M., Ikeda Y.
Neutron and Non-Neutron Nuclear Data for Radiation Dosimetry
Holden N.
New Measurements of the H(n,n)H Angular Distribution
Bateman F., Boukharouba N., Brient C., Carlson A., Grimes S., Haight R., Massey T., Wasson O.
Fission Cross Section Measurements of Th-229 and Pa-231 Using Linac-Driven Lead Slowing-Down Spectrometer
Kobayashi K., Yamamoto S., Kai T., Cho H., Yamana H., Fujita Y., Mitsugashira T., Kimura I.
Measurement of Differential Neutron-Induced Charged-Particle Emission Cross Sections for 5 – 75 MeV Neutrons
Baba M., Sanami T., Nauchi Y., Hirasawa Y., Hirakawa N., Nakashima H., Meigo S., Tanaka S.
Fast Neutron Yields Generated from Deuteron Break-up in Low Energy Reactions of Light Nuclei
Bém P., Burjan V., Cvachovec F., Götz M., Kroha V., Nikolskii E., Šimečková E., Štursa J., Vincour J.
Measurement of the Neutron Capture Cross-Sections for Dy and Hf between 0.001 eV and 50 keV Using Total Energy Absorption Detector
Cho H., Kobayashi K., Yamamoto S., Fujita Y., Kim G., Chang J., Ko S.
Modeling of BWR for Neutron and Gamma Fields Using PENTRAN™
Kucukboyaci V., Haghighat A., Sjoden G., Petrovic B.
Activity Determination with High Precision for Component Disposal
Polke E.
PV-Surveillance Dosimetry and Adjustment: Review of Several Significant Oral Laws
Perel R., Wagschal J., Yeivin Y.
Physically Constrained Adjustment of Calculated Neutron Spectra for Dosimetry and Vessel Locations
Williams J., Griffin P.
Algorithm and Computer Code of Group Neutron Spectra Transformation
Shimansky G., Tellin A., Gurevich M.
Improved Covariance Analysis and Spectrum Adjustment for VVER-1000 Pressure Vessel Fluences
Boehmer B., Borodkin G., Manturov G.
A Parametrized Approach for Unfolding the Neutron Flux Spectrum
Wang Y., Kobayashi K., Li Z., Kimura I.
Accuracy and Parallel Performance of PENTRAN™ Using the VENUS-3 Benchmark Experiment
Haghighat A., Abderrahim H., Sjoden G.
Three Dimensional Neutron Analysis in the Baffle-Former Area of PWR Plant
Kitagawa H., Yamagiwa N., Yamashita K.
MCBEND — A Fluence Modeling Tool
Wright G., Shuttleworth E., Cowan P., Curl I., Mattsson C.
Performance of A3MCNP™ for Calculation of 3-D Neutron Flux Distribution in a BWR Core Shroud
Haghighat A., Hiruta H., Petrovic B.
Development of 3D MCNP-Based BWR Fluence Computational Software Package: MF3D
Chiang R., Sitaraman S.
BWR Neutron Fluence Computations using MF3D
Sitaraman S., Chiang R., Kruger R., Jenkins A., Asano K., Koyabu K.
Development of Induced Activity Estimation Method for PWR Containment
Nakata M., Muramatsu T.
Comparative Analysis of DPA Processed from Current Evaluated Nuclear Data Libraries
Chang J., Gil C., Cho Y., Kim J.
JENDL PKA/KERMA File for IFMIF Project
Fukahori T., Chiba S., Shibata K., Ikeda Y., Aruga T., Watanabe Y., Murata T., Yamano N., Kawai M.
A Study of Displacement Cross Section in Medium-Energy Region
Iga K., Takada H., Ikeda Y.
Radiation Hardening in BWR Core Shrouds: Relative Roles of Neutron and Gamma Irradiation
Kwon J., Motta A.
Correlating Radiation Exposure with Embrittlement: Comparative Studies of Electron- and Neutron-Irradiated Pressure Vessel Alloys
Alexander D., Kestel B., Rehn L., Odette G., Lucas G., Klingensmith D., Gragg D., Seifert S., Jemian P.
The PKA Energy Spectrum Analysis of Defect Structures in Neutron Irradiated Metals
Yoshiie T., Xu X., Xu Q., Yanagita S., Satoh Y.
A Comparison of the NRT Displacement Model and Primary Damage Formation Observed in Molecular Dynamics Cascade Simulations
Stoller R., Greenwood L.
Fusion Neutron Irradiation Effects on Some Electronic Devices
Iida T., Tanimura Y., Sato F., Tanaka T.
Projects AMES Dosimetry and MADAM. Results and Future Activities
Ballesteros A., Debarberis L.
U.S. NRC Embrittlement Data Base (EDB)
Wang J., Pace J., Rosseel T.
Measurement of Eigenvalue Separation in Coupled-Core Systems using Optical Fiber with Scintillator
Unesaki H., Shiroya S., Hashimoto K., Horiguchi T., Takeda T., Yamamoto T., Kitada T., Aizawa O., Yamamoto J.
Selective and Prompt Self-Powered Neutron Detectors for Characterization of Mixed Radiation Fields in Reactors
Blandin C., Breaud S.
Neutron and Gamma Ray Dosimetry in Spent-Fuel Radiation Environments Using Silicon Carbide Semiconductor Radiation Detectors
Dulloo A., Ruddy F., Seidel J., Flinchbaugh T., Davison C., Daubenspeck T.
Retrospective Fast Neutron Dosimetry of Nuclear Power Plants by Means of Scraping Samples Using the 93Nb(n,n')93mNb Reaction
van Aarle J., Guenther I., Hegedues F., Gabler F.
A Novel Neutron Spectrometer with Response of Wide Energy Range
Uritani A., Makihara Y., Yamaguchi S., Kawarabayashi J., Iguchi T., Mori C., Toyokawa H., Takeda N., Kudo K., Sato O., Iwai S.
Characterization and Representation of the HPGE Detector Efficiency
Sparks M., Griffin P., Flanders T., Sallee W., Vehar D.
Accreditation and Certification in Radioactivity Measurement: Experience of the CEA/Reactor Dosimetry Laboratory
Royer J., Beretz D.
A Laser Compton-Scattered Photon Source for Potential Calibration of Gamma-Ray Detectors in the Energy Range from 2 to 22 MeV
Kudo K., Takeda N., Ohgaki H., Toyokawa H.
Stilbene Neutron Spectrometer with Spreading of a One Parameter Pulse Shape Discrimination Dynamic Range
Cvachovec F., Osmera B.
Use of Reaction 93Nb(n, n')93mNb to Determine Neutron Spectra at Outer PV Surface of WWER-1000 Reactor
Gritzay O., Rusinko P., Vasylyeva O.
Experimental Method of Neutron Spectra Determination with Activation Foils
Colomb F., Carcreff H., Morin C.
Qualifying C8/F9 Spectrum Index Measurements by Using Standard Neutron Fields
van der Meer K., D'hondt P., Vandebroek R.
Metal Discs as Very Low Thermal Neutron Flux Monitors in Reactor Environment
Martínez Canet M., Hult M., Köhler M., Aït Abderrahim H., Marloye D.
Development of a Neutron and Gamma-Ray Flux Distribution Measurement System with Scintillator and Optical Fiber Combination
Mori C., Uritani A., Iguchi T., Hayashi S., Kobayashi H., Takami Y., Kimura I., Katagiri M., Kakuta T.
Real-Time Dosimetry Method Using an Imaging Plate
Sakasai K., Katagiri M., Kishimoto M., Fujii Y.
Application of Accumulative Type ESR-Sensors for Determination of Intensity, Spectral Characteristics and Volume Distribution of Intense Gamma and Neutron Fields
Usatyi A., Kajnov V., Serdyukova L., Khamidov A.
Neutron Dosimetry Using Diallyl Phthalate Resin
Tsuruta T.
Development of In-Core Monitoring System using Optical Fiber for Advanced Fission Reactor
Kakuta T., Ishihara M., Shikama T., Narui M., Sagawa T., Arai T., Hayashi K.
Development and Modeling of Neutron Detectors for In-Core Measurement Requirements in Nuclear Reactors
Blandin C., Bignan G., Lebrun A., Poujade O., Recroix H., Eymery S., Trapp J., Breaud S.
Reduction of Inter-Event Dead Time in Data Acquisition System for Simultaneous Measurement of Neutron Pulse Series in Time and Space
Kitamura Y., Misawa T., Unesaki H., Shiroya S., Ishitani K., Uritani A., Yamane Y.
A System Design for Measuring Boron Concentration in Pressurized Light Water Reactor Cooling Water
Oda K., Kojima T., Nakagawa K., Yamauchi T., Ohashi S.
Appendices
Author Index
Subject Index
Committee: E10
Paper ID: STP1398-EB
DOI: 10.1520/STP1398-EB
ISBN-EB: 978-0-8031-5450-6
 ASTM International is a member of CrossRef.
0-8031-2884-3
978-0-8031-2884-2
STP1398-EB
|