| Radiation Shielding for Fission Reactors (p. 1) |
| by Oka, Y |
| Radiation Shielding for Fusion Reactors (p. 11) |
| by Santoro, R T |
| The Shielding of High-Energy Accelerators (p. 19) |
| by Stevenson, Graham Roger |
| Overview of Radiation Shielding Research (p. 27) |
| by Nakamura, T |
| Radiation Shielding and Protection of the European Spallation Neutron Source (ESS) (p. 30) |
| by Filges, D |
| The SNS Target Station Preliminary Title I Shielding Analyses (p. 35) |
| by Johnson, J O |
| JAERI-KEK Joint Project on High Intensity Proton Accelerators (p. 40) |
| by Nagamiya, S |
| Radiation Shielding Activities at the OECD/Nuclear Energy Agency (p. 49) |
| by Sartori, E |
| NEA Organized Validation of Multi-Dimensional Transport Codes and Cross-Section Sets Used Presently in Reactor Shielding (p. 53) |
| by Hehn, G |
| The UK Shielding Forum - Best Practice through Consensus (p. 58) |
| by Hobson, J |
| Shielding Experimental Benchmark Storage, Retrieval, and Display System (p. 61) |
| by Hunter, H T |
| Review of Contributions to the International Co-operation on Nuclear Data for Radiation Shielding (p. 68) |
| by Menapace, E |
| An Investigation of the Effects of Water Content on the Shielding Performance of the Primary Upper Shield in the High Temperature Engineering Test Reactor(HTTR) (p. 73) |
| by Sumita, J |
| Shielding Design for Steam Generator of Advanced Marine Reactor MRX (p. 78) |
| by Odano, N |
| Measurement of Shielding Characteristics in the Prototype FBR Monju (p. 83) |
| by Usami, S |
| Evaluation of the Shielding Design around the Reactor Core in the Prototype FBR Monju (p. 89) |
| by Shiraki, T |
| Evaluation of the Shielding Design of the Primary Cooling System in the Prototype FBR Monju (p. 94) |
| by Takeuchi, J |
| Evaluation of the Shielding Design of the Fuel Handling and Storage System in the Prototype FBR Monju (p. 99) |
| by Mikami, H |
| Evaluation of Neutron Streaming and Future Shielding Measurement Plan in the Prototype FBR Monju (p. 104) |
| by Sasaki, K |
| Shielding Design Study of the Demonstration Fast Breeder Reactor (1) - Evaluation of the JASPER Experiment and Its Analytical Results (p. 110) |
| by Handa, H |
| Shielding Design Study of the Demonstration Fast Breeder Reactor (2) - Shielding Design on the Basis of the JASPER Analysis (p. 115) |
| by Suzuoki, Z |
| A Fast Neutron Fluence Reduction Strategy for Pressure Vessel Lifetime Extension (p. 120) |
| by Kim, J K |
| Evaluation of Vessel Fluence for SMART by DORT and MCNP Codes (p. 125) |
| by Kim, K Y |
| A Preliminary Shielding Design of 150 MWe Liquid Metal Reactor (p. 130) |
| by Yoo, J W |
| Measurements of Thick Target Neutron Yields from 100 to 800 MeV /Nucleon Heavy Ions (p. 135) |
| by Kurosawa, T |
| Development of Heavy Ion Transport Monte Carlo Code (p. 142) |
| by Iwase, H |
| Shielding Design of RIKEN RI Beam Factory (p. 146) |
| by Uwamino, Y |
| Shielding and Handling of Targets for a High Intensity Radioactive Ion Beam Facility (p. 150) |
| by Moritz, L E |
| Shielding Calculations for the Proposed NISOL Facility at the ORNL Spallation Neutron Source (p. 154) |
| by Gallmeier, F X |
| Measurements of Neutron Attenuation through Iron and Concrete at ISIS (p. 158) |
| by Nunomiya, T |
| Deep Penetration Calculation Comparing with the Shielding Experiment at ISIS (p. 162) |
| by Nakao, N |
| MARS Code Developments, Benchmarking and Applications (p. 167) |
| by Mokhov, N V |
| Neutron Radiation at Muon Colliders and Storage Rings (p. 172) |
| by Mokhov, N V |
| Using the Moyer Model at Energies less than 1 GeV (p. 180) |
| by Moritz, L E |
| Depth Profiles of Radionuclides Induced in Shielding Concrete of the 12 GeV Proton Accelerator Facility at KEK (p. 183) |
| by Miura, T |
| Analysis of Iron and Concrete Shielding Experiments for 43 and 68 MeV p-^7Li Neutrons with LA150 (p. 187) |
| by Konno, C |
| Analyses of Neutron and Gamma Ray Measurements in a Target Room of Several Tens MeV Proton Facility (p. 192) |
| by Nakashima, H |
| Experimental Analyses on Radiation Streaming through a Labyrinth in a Proton Accelerator Facility of Several Tens MeV (p. 197) |
| by Nakashima, H |
| Experimental Setup for Measurements of High Energy Photo-Neutron Spectra from Thick Targets (p. 202) |
| by Sato, T |
| Photoneutron Spectra from Thin Targets Bombarded with 2 (p. 207) |
| by Lee, H S |
| 90^o Bremsstrahlung Source Term Produced in Thick Targets by 50 MeV to 10 GeV Electrons (p. 212) |
| by Mao, X S |
| Shielding Design Calculations for Laser Electron Photon Beamline of SPring-8 (p. 217) |
| by Asano, Y |
| Absorbed Dose from 7-GeV Bremsstrahlung in a PMMA Phantom (p. 222) |
| by Job, P K |
| A Study of Neutron Field Outside the Shielding Wall at SRRC (p. 226) |
| by Sheu, R J |
| Shielding Analysis of Nuclear Data Measurement Facility Using EGS4 and MCNP4 Codes (p. 231) |
| by Shin, C H |
| Radiation Shielding for ITER to Allow for Hands-on Maintenance Inside the Cryostat (p. 235) |
| by Iida, H |
| Measurement and Analysis of Neutron and Photon Flux Spectra in an ITER Shield Mockup with Open Channel and Cavity (p. 243) |
| by Unholzer, S |
| Dose Rate Analyses around the Equatorial and Divertor Ports during ITER in-Vessel Components Maintenance (p. 248) |
| by Mori, S |
| Estimation of Helium Production due to Neutron Streaming and Establishment of Shielding Design Conditions in Fusion Shielding Blanket by 3-D Mone Carlo Calculation (p. 253) |
| by Sato, S |
| Monte Carlo Analyses for ITER NBI Duct by 1/4 Tokamak Model (p. 258) |
| by Sato, S |
| Investigation on Prediction Capability of Nuclear Design Parameters for Gap Configuration in ITER through Analysis of the FNS Gap Streaming Experiment (p. 263) |
| by Maekawa, F |
| Neutron Streaming Evaluation for the DREAM Fusion Power Reactor (p. 268) |
| by Seki, Y |
| Neutronic Analysis of the KSTAR Tokamak Using Beowulf Cluster (p. 276) |
| by Park, J H |
| Shielding and Activation Calculations for the German Fusion Device WENDELSTEIN 7-X (p. 280) |
| by Quade, U |
| Radiation Shielding Analyses for JT-60SU (p. 284) |
| by Suzuki, Y |
| Evaluation of Nuclear Heat and Dose Rate for JT-60SU (p. 291) |
| by Mäki, K |
| Peculiarities of Forming the Neutron Field behind a Lengthy Shielding with Slits (p. 296) |
| by Tikhomirov, G V |
| Hot-Cell Shielding System for High Power Transmission in DUPIC Fuel Fabrication (p. 300) |
| by Kim, K |
| Shadow Shield Design Analysis for Repository Emplacement Drifts (p. 305) |
| by Su, S |
| Evaluation of Long-Term Irradiation Field in Geological Disposal of High-Level Radioactive Wastes (p. 310) |
| by Sawamura, H |
| Dose Analysis on High Performance Vault Storage System of Spent Nuclear Fuel (p. 316) |
| by Shibata, K |
| Evaluation of the Effect of Source Geometry Models on Dose Rates of Waste Packages (p. 320) |
| by Radulescu, G |
| Measurement of Dose-Equivalent Rates around a Cask and Monte Carlo Analysis with Actual Configuration of Fuel Basket (p. 324) |
| by Ueki, K |
| Shielding Benchmarks Analysis for Transport/Storage Casks (p. 329) |
| by Kitsos, S |
| Model and Method for Reasonable Shielding Calculation of Spent Fuel Casks (p. 334) |
| by Taniuchi, H |
| Shielding Designs and Tests of a New Exclusive Ship for Transporting Spent Nuclear Fuels (p. 337) |
| by Ono, M |
| Radiation Measurements and Shielding Calculations for Spent Fuel Casks (p. 342) |
| by Momma, Y |
| Shielding and Criticality Characterization of ALR8(SI) Plutonium Storage Containers (p. 347) |
| by Terekhin, Y V |
| Induced Activity Calculations in View of the Large Electron Positron Collider Decommissioning (p. 352) |
| by Fassò, A |
| Measurement of Residual Radioactivity of Machine Elements and Concrete on the Cyclotron Decommissioning (p. 357) |
| by Shiomi, T |
| Studies on Limestone Concrete as a Low-Activation Structural Material for Nuclear Power Plants (p. 362) |
| by Uematsu, M |
| Evaluation of Methodology on Radioactive Inventory Estimation in the Japan Power Demonstration Reactor Decommissioning Program (p. 367) |
| by Sukegawa, T |
| Shielding Analysis and Evaluation of JRR-2 Decommissioning (p. 372) |
| by Iwashita, M |
| Optimization of the BN (p. 379) |
| by Marek, M |
| Feasibility of a Neutron Beam for BN (p. 384) |
| by Cerullo, N |
| Feasibility of a Small Accelerator Driven Subcritical Reactor for BNCT Applications (p. 389) |
| by Montagnini, B |
| Mathematical Efficiency Calibration of in Vivo Measurement Systems (p. 394) |
| by Lee, T Y |
| A Simulation Study on the Dose Distribution for a Single Beam of the Gamma Knife (p. 397) |
| by Chen, C C |
| The Dose Distribution Inside the Irradiation Chamber of the Gamma Cell 220 at KACST Using MCNP4B (p. 402) |
| by Hefne, J |
| Application of Acceleration Techniques in MCBEND (p. 406) |
| by Shuttleworth, T |
| Adjoint Detector Calculations Using the Monte Carlo Code MCBEND (p. 412) |
| by Tee, M P |
| Uncertainty Analysis of Benchmark Experiments Using MCBEND (p. 416) |
| by Chucas, S |
| Treatment of Cross Section Uncertainties in the Transport Monte-Carlo Code TRIPOLI4 (p. 420) |
| by Both, J P |
| Neutronic Design of Pulse Operation Simulating Device for In-pile Functional Test of Fusion Blanket by MCNP (p. 423) |
| by Nagao, Y |
| Implementation of Surface Detector Option in Scale SAS4 Shielding Module (p. 427) |
| by Broadhead, B L |
| Biasing Techniques for Gamma Rays going around Efficient Shields (p. 432) |
| by Ghassoun, J |
| Study on Calculation of Detector Flux with Monte Carlo Methods (p. 436) |
| by Wang, R |
| Application of the Monte Carlo Method to Shielding Analysis in Medical Linear Accelerators (p. 441) |
| by Rodenas, J |
| Overview of Recent Research Activities of Monte Carlo Simulation in Japan (p. 446) |
| by Sakurai, K |
| Application of the Decoupling Scheme on Complex Neutron-Gamma Shielding Problems (p. 449) |
| by Fehér, S |
| Development of Angular Eigenvalue Method for Deep Penetration Problems of Gamma Rays (p. 454) |
| by Shimizu, A |
| New Transport Equation taking Account of the Momentum Conservation Law (p. 459) |
| by Taji, Y |
| Validation of the 3D Finite Element Transport Theory Code EVE (p. 466) |
| by Warner, P |
| GRTUNCL-3D : An Extension of the GRTUNCL Code to Compute R- theta -Z First Collision Source Moments(p. 471) |
| by Masukawa, F |
| FNSUNCL3 : First Collision Source Code for TORT(p. 475) |
| by Kosako, K |
| Activities Concerning a Re-Evaluation of Gamma-Ray Buildup Factors in Japan (p. 479) |
| by Hirayama, H |
| Gamma-Ray Buildup Factors for a Point Isotropic Source in the Single Layer Shield by Using BERMUDA Code (p. 484) |
| by Sakamoto, Y |
| An Improved Approximation Formula of Gamma-Ray Buildup Factors for a Point Isotropic Source in Two-Layer Shields (p. 488) |
| by Harima, Y |
| General Formalism for Calculating Gamma-Ray Buildup Factors in Mulirayer Shields info MERCURE-6 Code (p. 493) |
| by Assad, A |
| Calculation of Gamma Ray Buildup Factors for a Very Thick Slab with Angular Eigenvalue Method (p. 498) |
| by Kadotani, H |
| A Comparison of Gamma-Ray Buildup Factors for Water, Iron, and Lead Using Discrete Ordinates, Moments, and Monte Carlo Methods (p. 502) |
| by Assad, A |
| Calculation of Double Energy Angle Differential Neutron Albedos for Radiation Shielding Applications (p. 507) |
| by Litaize, O |
| On a New Point Kernel for Use in Gamma Radiation Calculations (p. 512) |
| by Bindel, L |
| Streaming Calculations using the Point-Kernel Code RANKERN (p. 515) |
| by Chucas, S |
| PERCEVAL v4 (p. 520) |
| by Bindel, L |
| Neutron Streaming Experiment for Radiation Shielding Hatch by ^2^5^2Cf Source (p. 522) |
| by Okuno, K |
| Attenuation of Neutrons and Total Gamma Rays in Two Layer Shields (p. 526) |
| by El-Bakkoush, F A |
| Systematic Comparisons of Measurements and EGS4 Regarding 20-40 keV Photons (p. 530) |
| by Namito, Y |
| Benchmark Experiment for Radiation Shielding around the Beam Dump of the SPring-8 Injector (p. 535) |
| by Asano, Y |
| Experimental Investigation on Streaming due to a Gap between Blanket Modules in ITER (p. 540) |
| by Konno, C |
| Measurements of the Neutron Spectrum in the 14 MeV Neutron Driven Vanadium-Alloy Assembly by the Multifoil Activation Method (p. 545) |
| by Uno, Y |
| Photon and Electron Shielding for Neptunium-237 (p. 550) |
| by Brown, T H |
| Decision-making Methodology of Optimal Shielding Materials by Using Fuzzy Linear Programming (p. 556) |
| by Kanai, Y |
| DOG - IV Revised Input Generator Program for DORT-TORT Code (p. 561) |
| by Saitou, M |
| Development of Nuclear Reaction Data Retrieval System on Meme Media (p. 566) |
| by Ohbayasi, Y |
| Derivation and Implementation of the Three-Region Problem in the SOURCES Code System (p. 570) |
| by Charlton, W S |
| ORIGEN-ARP, a Fast and Easy-to-Use Source Term Generation Tool (p. 575) |
| by Bowman, S M |
| Neutron/Gamma Ray Source Measurement and Analyses of High Burnup UO~2 /MOX Fuel Rods (p. 580) |
| by Matsumura, T |
| Evaluation of Buildup of Activated Corrosion Products for Highly Compact Marine Reactor DRX without Primary Coolant Water Purification System (p. 584) |
| by Odano, N |
| Calculation of the Isotope Concentrations, Source Terms and Radiation Shielding of the SAFARI-1 Irradiation Products (p. 589) |
| by Stoker, C C |
| Neutron Intensity Measurements of BWR Spent Fuels (p. 594) |
| by Tayama, R |
| Spatial and Energy Distributions of Skyshine Neutron and Gamma Radiation from Nuclear Reactors on the Ground-Air Boundary (p. 598) |
| by Orlov, Yu F |
| Using MCNP Code for Neutron and Photon Skyshine Analysis (p. 603) |
| by Zharkov, V P |
| Skyshine Analysis Using Various Nuclear Data Files (p. 606) |
| by Zharkov, V P |
| Comparison of Radiation Measurements and Calculations of Reactor Surroundings for Skyshine Analysis (p. 610) |
| by Tsubosaka, A |
| Improvement of Air Transport Data and Wall Transmission/Reflection Data in the SKYSHINE Code (1) - Calculation of line Beam Reponse Functions for Gamma-Ray Skyshine Analysis (p. 616) |
| by Nemoto, M |
| Improvement of Air Transport Data and Wall Transmission/Reflection Data in the SKYSHINE Code (2) - Calculation of Gamma-Ray Wall Transnission and Reflection Data (p. 621) |
| by Hayashida, Y |
| Application of Improved Air Transport Data and Wall Transmission /Reflection Data in the SKYSHINE Code to Typical BWR Turbine Skyshine (p. 626) |
| by Tayama, R |
| Development of "SKYSHINE-CG" Code : a Line-Beam Method Code Equipped with Combinatorial Geometry Routine(p. 631) |
| by Nakagawa, T |
| Modification of SKYSHINE-III to Include Cask Array Shadowing (p. 635) |
| by Hertel, N E |
| SHINE-III : Simple Code for Skyshine Dose Calculation up to 3 GeV Neutrons(p. 640) |
| by Tsukiyama, T |
| Effect of Source Angular Distribution on the Evaluation of Gamma-ray Skyshine (p. 645) |
| by Sheu, R D |
| Measurement of Secondary Gamma-Ray Skyshine and Groundshine from Intense 14 MeV Neutron Source Facility (p. 650) |
| by Yoshida, S |
| Neutron Leakage from Polyethylene Slit (p. 655) |
| by Mio, K |
| A Simple Method of Calculating Radiation Streaming through Cylindrical Ducts in a Concrete Shield (p. 660) |
| by Miura, T |
| Development of Simple Evaluation Method for Duct Streaming (p. 665) |
| by Mäki, K |
| Measurements and Calculations of the Dose Distribution from Co-60 Gamma Rays in Multiple Straight Ducts through Iron Shields (p. 670) |
| by Nariyama, N |
| 60-keV Gamma-Rays Streaming in a Two-Bend Duct (p. 675) |
| by Ban, S |
| Analysis of Neutron Streaming Experiment for Torus Duct by Cf-252 Neutron Source (p. 679) |
| by Kosako, T |
| Measurements of Elastic Scattering Cross Sections of Carbon, Silicon, Iron, Zirconium and Lead for 75 MeV Neutrons (p. 683) |
| by Ibaraki, M |
| Measurements of Double Differential Cross Sections of Secondary Charged-Particles Produced by Proton-Induced Reaction at Several Tens of MeV (p. 687) |
| by Harada, M |
| Measurements of Gamma-Ray Production Cross Sections and Spectra in Inelastic Interaction of 14 MeV Neutrons with Nuclei C, O, Mg, Al, Fe, Cu, Zr, Mo, W and Pb (p. 692) |
| by Nefedov, Yu A |
| Integral Data Test of FENDL-2 Fusion Nuclear Data Library with Neutronic Integral Experiments (p. 697) |
| by Wu, Y |
| Integral Test of Evaluated Nuclear Data for Zirconium, Lead and Bismuth Materials (p. 703) |
| by Blokhin, A I |
| Nuclear Data Validation and Re-Evaluation by Means of Integral Experiments (p. 708) |
| by Sublet, J C |
| Transport, Sensitivity and Uncertainty Analysis of FNG 14 MeV Neutron Bulk Shield Experiment (p. 713) |
| by Kodeli, I |
| Isotope Production Cross Section Library for Use of Transmutation Calculation in the IRAC Code System for the TIARA Facility (p. 718) |
| by Yamano, N |
| JSSTDL-300 : The Standard Shielding Cross Section Library Based on JENDL-3(p. 723) |
| by Hasegawa, A |
| Status of JENDL Photonuclear Data File and Intercomparison with Other Libraries (p. 728) |
| by Fukahori, T |
| Evaluation of Photonuclear Data of Mo, Zn, S and Cl for Medical and Accelerator Applications (p. 733) |
| by Lee, Y O |
| Evaluation of Gamma-Ray Production Cross-Sections for Inelastic Neutron Interaction with Aluminium and Lead (p. 738) |
| by Zvenigorodskii, A G |
| New Evaluations of the Gamma-Ray Production Cross Sections for Lead and Bismuth (p. 743) |
| by Blokhin, A I |
| Evaluation of Angular Distributions and Gamma-Ray Production Cross Sections for Iron (p. 748) |
| by Savin, M V |
| High-Energy Neutron Dosimetry (p. 753) |
| by Sutton, M R |
| Measurement of the gamma-Ray Dose around DAPhiNE Collider Using Different Types of High Sensitivity TLDs (p. 758) |
| by Angelone, M |
| Dosimetry at the Interim Spent Fuel Storage Facility of the Czech Nuclear Power Plant Dukovany (p. 762) |
| by Králik, M |
| Monte Carlo Simulation of X-Ray Induced Chromosomal Aberrations (p. 767) |
| by Shin, K |
| Measurements of Monochromatic Fluorescence X-ray Spectra (p. 771) |
| by Kim, J L |
| Optical Responses of alpha-Al~2O~3 : C by Multi-Wavelength Stimulation for Mixed Field Dosimetry(p. 776) |
| by Lee, S Y |
| Scattered Neutron Calibration Fields of KAERI (p. 781) |
| by Kim, B H |
| The Pulse Height Distribution Tally in MCBEND (p. 785) |
| by Shuttleworth, T |
| Development of Current Mode Time-of-Flight Technique for Measurement of Thermal Neutron Spectrum (p. 789) |
| by Meigo, S |
| Development of Self-TOF Neutron Detector and its Application to Shielding Experiment at HIMAC (p. 794) |
| by Sasaki, M |
| Effect of Aggregate Specification in Heavy Concrete for Fusion Reactor Shield on Neutron Dose Evaluation (p. 798) |
| by Murata, I |
| Development of Electronic Radiation Dosimeter Using Commercial Power p MOSFET (p. 803) |
| by Lee, N H |
| Chemical Warfare Agents Identification by Thermal Neutron Detection (p. 808) |
| by Liu, B |
| Measurement of Induced Radioactivity in Copper Exposed to High Energy Heavy Ion Beam (p. 811) |
| by Kim, E |
| Measurement and Analysis of Structural Activation in a Boiling Water Reactor (p. 816) |
| by Hayashida, Y |
| Studies on Induced Activities and Target Nuclei in Low-Activation Concrete Structure for Thermal Neutron Irradiation (p. 821) |
| by Kinno, M |
| Predicting Induced Radioactivity at High-Energy Electron Accelerators (p. 827) |
| by Fassò, A |
| The European Activation File : EAF-99 - JEFF-3 Activation File(p. 835) |
| by Sublet, J C |
| The IRAC Code System to Calculate Activation and Transmutation in the TIARA Facility (p. 840) |
| by Tanaka, S |
| DARWIN : An Evolution Code System for a Large Range of Applications(p. 845) |
| by Tsilanizara, A |
| Protection Quantities and Conversion Coefficients for Use in Radiation Shielding (p. 850) |
| by Pelliccioni, M |
| Overview of Fluence to Dose Conversion Coefficients for High Energy Radiations - Calculational Methods and Results of Two Kinds of Effective Dose per Unit Particle Fluence (p. 855) |
| by Iwai, S |
| Dose Contribution due to Photonuclear Reactions from High Energy Photon from 20 MeV to 10 GeV (p. 861) |
| by Sato, O |
| Fluence to Dose Conversion Coefficients for High-Energy Neutron, Proton and Alpha Particles (p. 865) |
| by Yoshizawa, N |
| Estimation of Activity and Dose Distributions around a Proton Linac Induced by Beam Spill (p. 870) |
| by Nakashima, H |
| Mammographic Dosimetry Using MCNP-4B (p. 875) |
| by Verdu, G |
| Seasonal Influence of Countermeasures for Milk after a Nuclear Accident (p. 880) |
| by Hwang, W T |
| Neutrino Radiation at Muon Colliders and Storage Rings |
| by Mokhov, N V |
| Optimization of shielding design from the target station of high power spallation neutron source |
| by Alexeev, A |
