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Digital Library / STP / STP1228-EB
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Reactor Dosimetry
Farrar H
Pages: 846
Published: 1994
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Table of Contents
Impact of U.S. NRC Reactor Vessel Embrittlement Research on Regulation of Nuclear Power Plants
Serpan CZ
Technical Issues Relevant to ASTM LWR Surveillance Standards
McElroy WN, McElroy RJ, Gold R
ASTM Standards Associated with PWR and BWR Power Plant Licensing, Operation and Surveillance
McElroy WN, McElroy RJ, Gold R, Lippincott EP, Lowe AL
VVER-440 Reactor Vessel Exposure Monitoring in the Czech Republic
Omera B, Svoboda , Hep J, Holman M, Hógel J, Valenta V
Neutron Fluence Determination for WER-440 Reactor Pressure Vessel Ageing Surveillance
Ilieva KD, Apostolov TG, Belousov SI, Antonov SY
Revision of Neutron Dosimetry for the Loviisa WER-440 Reactors: Principles and Application
Baers LB, Serén T0
Pressure Vessel Fluence Monitoring at NPP with VVER: Routine Technique and New Approaches
Borodkin GI, Kovalevich OM, Lomakin SS, Sycheva NV
Analysis of the TIHANGE-2 Surveillance Neutron Dosimetry Using the Lepricon Code System
Abderrahim HA, Minsart GL, D'hondt PJ
Lepricon, Combination of Correlated Data and Peelle's Puzzle
Perel RL, Wagschal JJ, Yeivin Y
Assessment of Uncertainty in Reactor Vessel Fluence Determination
Lippincott EP
Investigations into Power Reactor Fluence Uncertainties and their Implications for Trend Curves
Helm JL
Neutron Fluence Determination for Light Water Reactor Pressure Vessels
Gold R
Maine Yankee Dosimetry Capsule and Pressure Vessel Neutron Fluence Calculations
White JR, Spinney KB, Morrissey KJ, Cacciapouti RJ
Analysis of PWR Pressure Vessel Surveillance Dosimetry with McBend
de Wouters RM, Laurent DJ, D'Hondt PJ
Special Dosimetry at Saint Laurent BL Mox-Loaded Unit
Bevilacqua A, Lloret R, Nimal JC, Zengh S, Rieg C
Three-Dimensional Discrete Ordinates Radiation Transport Calculations of Neutron Fluxes for Beginnig-of-Cycle at Several Pressure Vessel Surveillance Positions in the High Flux Isotope Reactor
Pace JV, slater CO, Smith MS
Fluence Surveillance by Scraping Samples from the Inner Surface of the Thermal Shield in the Nuclear Power Plant Obrigheim in Germany (KWO).
Polke E
Koeberg Surveillance Capsule Fluence Determination Using PCDC Dosimetry Cross Sections and Activation Measurements
Stoker CC, Reitsma F, Lamparelli G
Boron Determinations in Pressure Vessel Steels
Oliver BM, McElroy WN, Kellogg LS, Farrar H
Neutron Dosimetry with the Ni(n,p)Co Reaction at Short-Decay Times
Griffin PJ, Holm CV, Vehar DW, Kelly JJG
Mono-Energetic Mono-Directional Resonance Neutron Activation of Natural Indium Metal Target
Ertek C, Oigawa H
Passive Temperature Monitoring in Reactor Environments Using Integrating Thermal Monitors
Ruddy FH, Seide JG, Fero AH
Neutron Flux Estimations Based on Niobium Impurities in Reactor Pressure Vessel Steel
Baers LB, Hasanen EK
Neutron Dosimetry and Mechanical Properties Changes Monitoring by Magnetic Response of Fe and Ni Wires
Shong W-J, Stubbins JF, Williams JG, Rogers JW, Giacobbe M
Applicability of Superheated Drop (Bubble) Detectors to Reactor Dosimetry
d'Errico F, Alberts WG, Apfel RE, Curzio G, Guldbakke S
Materials Prepared at the Institute for Reference Materials and Measurements (IRMM) for Reactor Dosimetry Applications
Ingelbrecht CD, Peetermans FW, Palmeri S, Robouch PB
Signal Anticipation of Rhodium Self Powered Neutron Detectors for On-Line Applications
Lacaille R, Jegat A
Dynamic Compensation of the Silver Self-Powered Neutron Detector in the Ramp Program at the Osiris Reactor
Moulin DJ
Research for Application of Long Counter with a Position-Sensitive Proportional Counter to Neutron Dosimetry
Toyokawa H, Uritani A, Mori C, Takeda N, Kudo K
The Modified Notched Neutron Spectrum Technique for the Surveillance of Hydrogen in Reactor Materials
Miller WH
Response Matrices of NE213 Scintillation Detectors for Neutrons
Guldbakke S, Klein H, Meister A, Pulpan J, Scheler U, Tichy M, Unholzer S
Accurate Neutron Fluence Measurements Using Bonner Spheres
Alevra AV
Proton Recoil Spectroscopy 400 Meters from a Fission Neutron Source
Stanka MB
Neutron Fluence Determination at Reactor Filters by He Proportional Counters: Comparison of Unfolding Algorithms
Matzke M, Alberts WG, Dietz E
Analysis of the Venus Out-Of-Core Activation Measurements Using MCBEND
Blaise PD, de Wouters RM, Abderrahim HA
Analysis of the VENUS-1 Ex-Core Neutron Dosimetry Using the Lepricon Code System
Abderrahim HA, Hort M
Test Calculations of the Neutron Flux on VVER-1000 Reactor Pressure Vessel
Ilieva KD, Belousov SI, Antonov SY, Zaritsky SM, Brodkin EB
Analysis of Pulsed-Sphere Experiments as Integral Data for Cross-Section Adjustment
Perel RL, Wagschall JJ, Yeivin Y
Evaluation of the Results of the B&W Owners Group Cavity Dosimetry Benchmark Experiment
Petrusha L, Garat C
Neutron Leakage Benchmarks for Water Moderators
Gilliam DM, Briesmeister JF
Pool Critical Assembly Benchmark Solutions Using MCNP and Threedant
Urban WT, Alcouffe RE, Parsons DK, Marr DR, Clark BA
Validation of Neutron Transport Calculations on Magnox Power Plant
Mossop JR, Thornton DA, Lewis TA
Concrete Benchmark Experiment as Support to Ex-Vessel LWR Surveillance Dosimetry
Abderrahim HA, Dhondt PJ, Risch P, Oeyen JB, Bioux P
The Materials Dosimetry Reference Facility
Hawari AI, Venkataraman R, Fleming R, Charles E, Grundl J, McGarry ED
SILENE, a New Radiation Reference Source
Rozain JP, Barbry F, Medioni R
Development of an Alanine Dosimeter for Gamma Dosimetry in Mixed Environments
Vehar DW, Griffin PJ
Reusability of CaF:Mn Thermoluminescence Dosimeters for Photon Irradiations at High Absorbed-Dose Levels
Vehar DW
Gamma-Ray Dose Mapping in Operational CANDU Reactor Containment Areas Using MOS Dosimeters
Mackay G, Thomson I, Hirning CR, Zeya M
Characterization of the Gamma Field in the B%W Owners Group Cavity Dosimetry Benchmark Experiment
King SQ, Gilliam DM
Measurement and Analysis of Gamma-Ray Distributions in Kyoto University Critical Assembly, KUCA
Kimura I, Kagehira K, Sakurai Y, Kimura J, Kanno I, Sato T, Shiroya S, Kanda K
Overview of the Activities in Spain on Irradiation Embrittlement of RPV Steel
Bros J, Ballesteros A
Neutron Spectrum Effect on Pressure Vessel Embrittlement: Dosimetry and Qualification of Irradiation Locations in Osiris and Siloe Reactors
Alberman A, Beretz D, Bourdet L, Carcreff H
The Irradiation Facility Korpus for Irradiation of the Reactor Structure Materials
Brodkin EB, Egorov AL, Golovanov VN, Markina NV, Raetsky VM, Sulaberidze VS, Tsikanov VA, Zaritsky SM
Reactor Vessel Dosimetry Assessment: Perspectives of the Materials Engineer
Steele LE, Beaudoin BF, Biemiller EC, Van Konynenburg RA, Server WL
Calculation of Transmutation in Copper and Comparison with Measured Electrical Properties
Greenwood LR, Garner FA, Edwards DJ
Intercomparison of Neutron Test Facilities for Equivalent Damage to Electronics
Heimbach CR
The Test Reactor Embrittlement Data Base (TR-EDB)
Stallmann FW, Kam FBK, Wang JA
Calculated Damage Rates for FFTF Structural Components and Surveillance Assemblies
Simons RL
A Plant-Specific Upper Shelf Energy Drop Methodology
Manahan MP, Cuddy LJ, Peterson AJ
Calculated and Measured Gas Formation in Beryllium Samples Irradiated in the High Flux Materials Testing Reactor BR2
De Raedt CM, Sannen LF, Vanmechelen PJ, Oliver BM
The Spallation Neutron Source SINQ and Related Dosimetry Problems
Janett A, Atchison F, Bauer GS
Dosimetry Issues for an Ultra-High Flux Beam and Multipurpose Research Reactor Design
West CD
Investigation of Laboratory Neutron Spectral Characterizations Used for the Testing of Electronic Parts
Kelly JJG, Griffin PJ, Raupach DC, Daubenspect TH, Bennion JS, Newell DL
Dosimetry Aspects of the New Canadian MAPLE-X10 Reactor
Lidstone RF, Wilkin GB
Neutron Metrology in the Fuel Assemblies of a Material Test Reactor.
Voorbraak WP, Paardekooper A, Polle BN, Freudenreich WE
Two-Dimensional Neutron and Gamma Calculations for Devices Irradiated in BR2 Reflector Positions
De Raedt CM, Bodart SF, Ponsard BJ, Wéber MJ, Maldague T
Energy and Spatial Distribution of the Photoneutron Flux from a Radiotherapy Electron Accelerator
Agosteo S, Foglio Para A
Determination of the Neutron Flux for the Yankee Rowe Experiment in the Ford Nuclear Reactor
Cacciapouti RJ, Petrusha L
Testing of the IRDF-90 Cross-Section Library in Benchmark Neutron Spectra
Nolthenius HJ, Zsolnay éM, Szondi EJ
Comparison of the BUGLE-80 and SAILOR Libraries for Coupled Neutron-Gamma Transport Applications
White JR, Spinney KB, Morrissey KJ, Cacciapouti RJ
Production and Testing of the Vitamin-B6 Fine-Group and the BUGLE-93 Broad-Group Neutron/Photon Cross-Section Libraries Derived from ENDF/B-VI Nuclear Data
Ingersoll DT, White JE, Wright RQ, Hunter HT, Slater CO, MacFarlane RE, Greene NM
JENDL Dosimetry File
Kobayashi K, Nakazawa M, Iwasaki S, Iguchi T, Ikeda Y, Nakagawa T, Sakurai K, Odano N
Status of Neutron Dosimetry Cross Sections
Griffin PJ, Kelly JJG
Nuclear Data Needs for Fission Reactor Decommissioning
Kocherov NP
Evaluation of the Nb(n,n') Nb and Nb(n,2n) Nb Reactions Cross-Sections from Threshold to 20 MEV.
Badikov SA, Zolotarev KI
Measurements of the Np(n,f) Cross Section
Carlson AD, Parker WE, Lisowski PW, Morgan GL, Seestrom SJ, Hill NW, Meggers K
Measurements of Thermal Neutron Cross Section and Resonance Integral for the Np(n,)Np Reaction
Kobayashi K, Yamanaka A, Kimura I
Measurement of U Fission Spectrum-Averaged Cross Sections for Some Threshold Reactions
Kobayashi K
Calculation of Cobalt and Gold Dosimetry Cross Sections from 1 to 50 MeV
Iwasaki S, Odano N
Measurement and Analysis of the Nitrogen Total and Differential Scattering Cross Sections in the Resonance Region
Beasley CO, Larson NM, Harvey JA, Larson DC, Hale GM
Effect of Gadolinium Covers on Fast Dosimeter Response
Rutherford MA, King SQ
The DS86 Neutron Dosimetry Enigma: Some Missing Pieces to the Puzzle
Gold R
Helium Measurements in Support of MHTGR Lithium Target Testing
Oliver BM, Rogers JW
Design of a Target and Moderator at the Los Alamos Spallation Radiation Effects Facility (LASREF) as a Neutron Source for Fusion Reactor Materials Development
Ferguson PD, Mueller GE, Sommer WF, Farnum EH
Spallation Radiation Damage and Dosimetry for Accelerator Transmutation of Waste Applications
Wechsler MS, Ferguson PD, Lin C, Sommer WF
Neutron Dosimetry and Activation on the Tokamak Tore-Supra
Joyer P, Martin G
Dosimetry of Medium Energy Neutrons and Protons in Material Irradiation Experiments
Hegedüs F, Victoria M
Neutron Cross Sections for the Interpretation of a Spallation Experiment
Bortignon PF, Mariani F, Perini A, Sangiust V
Author Index
Subject Index
Committee: E10
Paper ID: STP1228-EB
DOI: 10.1520/STP1228-EB
 ASTM International is a member of CrossRef.
0-8031-1899-6
978-0-8031-1899-7
STP1228-EB
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