Number
YGN
Title
001
DEVELOPMENT, OPTIMIZATION, AND HARMONIZATION OF INNOVATIVE TECHNIQUES FOR RADIOACTIVE WASTE CHARACTERIZATION WITHIN THE EURAD-2 PROGRAMME
002
Innovative and new Container/canister materials under disposal field conditions: Manufacturing feasibility and improved Durability – the InCoManD project (WP9) of the EURAD-2 partnership
003
MODELLING OF TEMPERATURE-CONTROLLED TRIAXIAL COMPRESSION TESTS TO SUPPORT ANALYSIS OF CALLOVO-OXFORDIAN ARGILLITE BEHAVIOR
004
SUDOKU: NEAR-SURFACE DISPOSAL OPTIMIZATION BASED ON KNOWLEDGE AND UNDERSTANDING
005
DEVELOPMENT AND IMPROVEMENT OF THERMODYNAMIC UNDERSTANDING FOR USE IN NUCLEAR WASTE DISPOSAL SAFETY CASE
006
ygn
INCREASING THE TEMPERATURE OF THE CANISTER SURFACE TO 150°C: EFFECT ON THERMO-HYDRAULIC PROCESSES IN THE BENTONITE BARRIER
007
NUMERICAL ANALYSIS OF NEUTRON ACTIVATION PROCESSES IN CLADDING MATERIAL OF SPENT FUEL ROD
008
TOWARDS HIGH FIDELITY NUMERICAL SIMULATIONS OF STRONGLY COUPLED PROCESSES FOR REPOSITORY SYSTEMS
009
EXPERIMENTAL STUDY OF THE IMPACT OF SELF-SEALING ON THE WATER AND GAS PERMEABILITY OF FRACTURES IN CALLOVO-OXFORDIAN CLAYSTONE
010
ANALYSIS OF THE IMPACT OF CLIMATE CHANGE ON NUCLEAR WASTE MANAGEMENT
011
DIRECT IMMOBILISATION OF LIQUID ORGANIC RADIOACTIVE WASTE IN A GEOPOLYMER MATRIX
012
INTERACTIONS WITH CIVIL SOCIETY IN EURAD
014
ANCHORS -HYDRAULIC MECHANICAL CHEMICAL EVOLUTION OF BENTONITE FOR BARRIERS OPTIMISATION
015
EURAD-2 STRATEGIC STUDY “ASTRA” – ALTERNATIVE WASTE MANAGEMENT STRATEGIES
016
EURAD WP15 CONCORD: AN OVERVIEW OF 3 YEARS OF JOINTLY COORDINATED CANISTER MATERIALS R&D
017
EURAD2-L’OPERA: ASSESSMENT OF THE LONG-TERM PERFORMANCE OF INNOVATIVE WASTE MATRICES FOR THE IMMOBILIZATION OF LOW- AND INTERMEDIATE-LEVEL RADIOACTIVE WASTE
018
High-level Waste deep repository optimisation including closure – a strategic study within EURAD 2
019
Next generation Digital Twins to support Optimisation, Construction and Operation of surface and subsurface radioactive waste management facilities - DITOCO2030
020
Effects of Nuclear Disasters on Animals and Risk Management with the Rotating Wing Animal Detection System
021
Environmental Impacts of Coastal Nuclear Power Plants: The Role of Early Warning Systems in Managing Radioactive Contamination
022
Autonomous Mobile Laboratory for Comprehensive Radiation, Pollution, and Chemical Detection in Marine Environments
023
MICROSTRUCTURAL STUDY OF HELIUM BUBBLE FORMATION AND TRAPPING IN OXIDE DISPERSION-STRENGTHENED STEELS FOR FUSION REACTOR APPLICATIONS
024
INNOVATION IN RADIOACTIVE SOLID ORGANIC WASTE TREATMENT AND CONDITIONING IN THE FRAMEWORK OF THE PREDIS PROJECT ON PREDISPOSAL WASTE MANAGEMENT
025
INVESTIGATION ON THE USE OF YELLOW TUFF IN ACIDACTIVATED GEOPOLYMERS FOR RADIONUCLIDES IMMOBILISATION
026
SLEEVELESS FUEL COMPACT SUPPORT: SPACER DESIGN AND FLOW-INDUCED VIBRATION ANALYSIS IN HTGR
027
EFFECT OF THE NEW TYPE FUEL ON THE NUCLIDES CONCENTRATION CHANGE AND THE DECAY HEAT PRODUCTION IN REACTORS
028
INVESTIGATION OF NATURAL CIRCULATION IN EXPERIMENTAL HELIUM LOOP
029
EURAD-2 FORSAFF ACTIVITIES ON SMR WASTE MANAGEMENT
030
CRITICALITY SAFETY FOR FINAL DISPOSAL IN EURAD-2
031
Plasma gasification of SPENT ion exchange resins and the ash conditioning in Geopolymer matrix
032
GAMMA IRRADIATION STABILITY OF NOVEL BINDERS FOR RADIOACTIVE LIQUID ORGANIC WASTE IMMOBILIZATION
034
HARPERS - CONDITIONS AND OPPORTUNITIES FOR PROMOTING CIRCULAR ECONOMY APPROACHES IN NUCLEAR DECOMMISSIONING AND RADIOACTIVE WASTE MANAGEMENT
035
Earthquake Precursor Measurements Employing a Network of Radon Sensors
036
ENHANCING SEVERE ACCIDENT MANAGEMENT THROUGH RESEARCH
037
STRENGTHENING NUCLEAR POWER THROUGH INNOVATION IN SAFETY ANALYSIS
038
MAIN RESULTS AND IMPACT FROM THE WP CORI IN EURAD
039
RAMPEC: A WORKPACKAGE IN EURAD-2 FOCUSING ON RADIONUCLIDE MOBILITY UNDER PERTURBED CONDITIONS
040
EURADSCIENCE – AN INTERNATIONAL NETWORK OF RESEARCH ORGANISATIONS IN EUROPE ON RADIOACTIVE WASTE MANAGEMENT
041
EURAD-2 WP SAREC: Release of safety relevant radionuclides from spent nuclear fuel under deep disposal conditions
042
APPLICATION OF MONTE CARLO MODELING AND COMPTON-TO PEAK RATIO ANALYSIS OF GAMMA SPECTRA FOR THE EVALUATION OF ACTIVITY BEFORE AND AFTER METALLIC RADIOACTIVE WASTE DECONTAMINATION PROCEDURE
043
APPLICATION OF OPTIMIZED NUCLIDE VECTOR FOR RADIOACTIVE WASTE MANAGEMENT
044
HARPERS WP4.2C – GUIDELINES FOR COMPARING CIRCULAR AND LINEAR ECONOMY APPROACHES TO NUCLEAR DECOMMISSIONING
045
Strategic Knowledge Management for Radioactive Waste Disposal: A Review of EURAD and PREDIS
046
KNOWLEDGE APPLICATION AND KNOW-HOW DEVELOPMENT WITHIN EURAD-2 JOINT PROGRAMME ON RADIOACTIVE WASTE MANAGEMENT
047
EUROPEAN COMMISSION INVOLVEMENT IN MULTINATIONAL REPOSITORY INITIATIVES
048
Advanced technology fuels material property models implementation in the TRANSURANUS platform
049
PREDIS: HOW STAKEHOLDER ENGAGEMENT INFLUENCED THE PREDIS PROJECT AND MAXIMIZED THE VALUE AND IMPACT– LEADING TO IMPROVED SUSTAINABILITY IN RADIOACTIVE WASTE MANAGEMENT
050
PUBLIC AWARENESS OF SMR: CHALLENGES AND OPPORTUNITIES FOR NUCLEAR POWER IN THE ENERGY TRANSITION
051
Education and Training for Leaders in Nuclear Decommissioning Projects
052
TRANSPOSITION STUDIES WITH A HYBRID EXPERIMENTAL BASE COMBINING ZPR AND PWR MEASUREMENTS
053
iRE-SOLVE PROCESS: AN INVENTIVE SOLUTION TO ADDRESS THE PRE-DISPOSAL OF ION-EXCHANGE RESINS
054
DIRECT IMMOBILIZATION OF REAL RADIOACTIVE LIQUID ORGANIC WASTE IN NOVEL GEOPOLYMERS: OUTCOMES FROM THE PREDIS PROJECT
055
RIMAX, AN AUTOMATED X-RAY MAPPING TOOL TO SURFACE CHARACTERIZATION
056
PERSPECTIVES FOR Tb-161 RADIOPHAMACEUTICALS LOCAL PRODUCTION AT ENEA TRIGA RC-1 REACTOR IN ROME
057
AlphaMet project - Metrology for emerging targeted alpha therapies at NCNR RC POLATOM
058
059
THE SECURE PROJECT, A CONTRIBUTION TO A STABLE SUPPLY OF MEDICAL RADIOISOTOPES IN EUROPE
060
ETERE: A PORTABLE RADIOACTIVE AEROSOL MONITOR CAPABLE OF FAST ALARM RESPONSE AND QUANTITATIVE SPECTROMETRIC ANALYSIS OF ARTIFICIAL ALPHA EMITTERS
061
TERBIUM-161, IRRADIATION, SEPARATION AND RECOVERY OF TARGET MATERIAL
062
EUROPEAN SEVERE ACCIDENT RESEARCH FACILITIES: MAPPING AND ANALYSIS
063
EXPERIENCE ON THE IMMOBILISATION OF ION EXCHANGE RESINS IN GEOPOLYMERIC AND ALKALI-ACTIVATED MATERIALS: SPANISH EXPERIMENTAL PROGRAMME
064
CONCEALED PIPING INTEGRITY ASSESSMENT WITHIN UKRAINIAN NPPS LTO JUSTIFICATION
065
ADDRESSING CHALLENGES IN THE NUCLEAR FUEL CYCLE BACK-END: NEA’S COMPREHENSIVE APPROACH
066
THE STRUCTURAL, ELECTRONIC, AND OPTICAL PROPERTIES OF ANORTHITE CaAl₂Si₂O₈
068
DEVELOPMENT OF AN ANALYTICAL PROTOCOL FOR THE DETERMINATION OF DIFFICULT TO MEASURE RADIONUCLIDES IN STEEL
069
JÓVENES NUCLEARES: ONE MORE YEAR BREATHING NUCLEAR SCIENCE AND TECHNOLOGY
070
From robots to drones, the future of decommissioning operations – The CLEANDEM and XS ABILITY projects
071
Robots, drones and innovative radiation sensors, the future of unmanned operations with the XS ABILITY project
072
PVD metallic and ceramic coatings affecting corrosion protection of steel containers for nuclear waste in a deep geological repository
073
INNOVATIVE MATRIX FOR RADIACTIVE WASTE CONDITIONING; GEOPOLYMERS AND DIATOMACEOUS EARTH
074
Fast reactors are flexible towards the plutonium management : the European project PuMMA has provided demonstrations.
075
TOWARDS A EUROPEAN SEVERE ACCIDENT INFRASTRUCTURE NETWORK (SAINET): AN OUTCOME OF THE SEAKNOT PROJECT
076
LEVERAGING AI FOR ENHANCED EFFICIENCY AND SAFETY IN NUCLEAR PLANTS: FOCUS ON OPERATIONAL PERFORMANCE, FLEXIBILITY, AND DECOMMISSIONING
077
ASSESSMENT OF RADIATION SHIELDING PROPERTIES OF INNOVATIVE CONCRETE WITH OIL SHALE ASH AND BASALT-BORON FIBER ADDITIVES
078
INVESTIGATION OF THE PROCESSES IN THE SPENT FUEL DURING INTERIM STORAGE IN IGNALINA NPP
079
MODELLING OF NATURAL CIRCULATION IN PMK-2 EXPERIMENTS USING RELAP5 CODE
080
A CERAMIC CONTAINER PRODUCED BY GELCASTING: AN ALTERNATIVE CONCEPT FOR THE DISPOSAL OF HIGH-LEVEL RADIOACTIVE WASTE?
081
Site selection procedure for high-level radioactive waste: Considerations for optimization in accordance with the principles of the German Site Selection Act
082
CHALLENGES ON WASTE MANAGEMENT AT DECOMMISSIONING BY ENRESA: NEW SOLUTIONS, STRATEGIES AND INNOVATION
083
NEUTRONIC ANALYSIS OF ACCIDENT TOLERANT FUEL CONCEPTS IN SPECTRAL SHIFT REGULATION CONDITIONS
084
WAITING FOR THE REPOSITORY – DRY STORAGE ACTIVITIES AT PSI
085
DESIGN OF THERANOSTIC RADIOPHARMACEUTICALS FOR ENHANCED DRUG DELIVERY
086
MACHINE LEARNING BASED MODELS FOR HPC THERMOMECHANICAL FUEL ASSESSMENT
087
EFFICIENT PREDICTION OF DUCTILE FRACTURE IN FERRITIC STEELS USING ARTIFICAL NEURAL NETWORK
088
ASSESSMENT OF GAUSSIAN AND LAGRANGIAN DISPERSION MODELS IN JRODOS FOR DIFFERENT TERRAINS AND SOURCE TERMS
089
ADVANCED METHODS FOR DETERMINING EMERGENCY PLANNING ZONES FOR INNOVATIVE SMALL REACTOR DESIGNS
090
ARMED CONFLICT AND NUCLEAR SECURITY: IMPLICATIONS FOR EUROPE
091
POLYMERS IN NUCLEAR POWER
092
THE SECURE PROJECT: TOWARDS A STABLE EUROPEAN SUPPLY OF MEDICAL RADIOISOTOPES
093
Mechanical Performance of NiFeCrMn Alloy Under Tensile Loading: An Experimental and Atomistic Model
094
EURAD-2 WP6 STREAM: SUSTAINABLE TREATMENT AND IMMOBILISATION OF CHALLENGING WASTE
095
SORPTION MECHANISMS OF 137Cs IN SOIL: IMPLICATION AND OPPORTUNITY FOR ENVIRONMENTAL REMEDIATION
096
Gamma radionuclides in tobacco plant processing
097
LONG-TERM MONITORING OF GALVANIC CURRENTS OF COPPER-STEEL COUPLING IN AN ANOXIC ENVIRONMENT
098
TREATMENT OF RADIOACTIVE AQUEOUS SOLUTIONS BY ADSORPTION ON FLY ASH AND SYNTHETIC ZEOLITES
099
GEOPOLYMER FROM DOMESTIC WASTE PRODUCTS FOR THE MANAGEMENT OF LIQUID RADIOACTIVE WASTES
100
DEVELOPMENT OF SMR TECHNOLOGY IN POLAND - MANAGEMENT OF RADIOACTIVE WASTE AND SPENT NUCLEAR FUEL
101
STRUCTURAL CHARACTERIZATION OF URANIUM AND LANTHANIDE LOADED BOROSILICATE GLASS MATRIX
102
TRANSITION METAL SORPTION ON BENTONITE AND BEHAVIOUR OF THE BENTONITE/COPPER/GLASS BARRIER SYSTEM
104
DISSOLUTION OF UNIRRADIATED MOX FUEL IN THE PRESENCE OF METALLIC IRON
105
INNOVATION IN NUCLEAR ENERGY DEVELOPMENT: ANALYZING THE BUILD-OWN-OPERATE MODEL IN THE TÜRKIYE-RUSSIA NUCLEAR POWER PLANT PROJECT
106
POWERING SPACE EXPLORATION: Np-237 TARGET MANUFACTURING
107
TRANSFORMING SAFETY, SIMULATION, AND COLLABORATION IN THE NUCLEAR RESEARCH THROUGH IMMERSIVE VIRTUAL REALITY
108
INVESTIGATION OF RADIATION STABILITY OF THE RESORCINOL-FORMALDEHYDE RESIN FOR 60CO RADIONUCLIDE REMOVAL.
109
KIT CONTRIBUTION TO THE MULTIPHYISCS R&D ACTIVITIES WITHIN THE H2020 EU CAMIVVER PROJECT
110
LASER-ASSISTED JOINING OF SIC/SIC COMPOSITES USING SAY (SILICA ALUMINA YTTRIA) FOR HIGH-PERFORMANCE NUCLEAR APPLICATIONS
111
Terrorist Threat Analysis for Nuclear Infrastructure: Case Studies and Lessons for Safety
112
NUMERICAL VISUALIZATION OF GAMMA RADIATION DISTRIBUTION IN NUCLEAR DECOMMISSIONING PROCESSES
113
POOL-LOOP: EXPERIMENTAL FACILITY FOR NATURAL CONVECTION FLOW IN A POOL WITH IMMERSED HEAT EXCHANGERS (PASSIVE SYSTEM)
114
HUMAN RESOURCE DEVELOPMENT FOR RADIATION SAFETY IN MOLTEN SALT REACTORS
115
MOLTEN SALT REACTORS AS A WASTE MANAGEMENT STRATEGY FOR SPENT FUEL
116
EMPOWERING EUROPE'S ENERGY TRANSITION: STRATEGIC MANAGEMENT AND ENVIRONMENTAL RESPONSIBILITY IN MSR IMPLEMENTATION
117
ADVANTAGES OF A CENTRALIZED FACILITY FOR SPENT FUEL AND WASTE MANAGEMENT
118
EMERGENCY RESPONSE STRATEGIES FOR A SAFE OPERATION OF MOLTEN SALT REACTORS
119
COMMUNICATION STRATEGY FOR A NUCLEAR SPENT FUEL AND WASTE MANAGEMENT FACILITY FOR MOLTEN SALT REACTORS
120
EMERGENCY PREPAREDNESS FOR SMR WASTE MANAGEMENT IN EU DISTRICT HEATING
121
CENTRALIZED FACILITY FOR SPENT FUEL AND WASTE MANAGEMENT
122
SMR DEPLOYMENT FOR DISTRICT HEATING DECARBONIZATION IN EUROPE, FROM A LINCENCING PERSPECTIVE
123
STAKEHOLDER ENGAGEMENT FOR THE DEPLOYMENT OF FLOATING NUCLEAR POWER PLANTS IN NORDIC REGIONS
124
CAPACITY BUILDING AND WORKFORCE DEVELOPMENT FOR FLOATING NUCLEAR POWER PLANTS IN NORDIC REGION
125
UNLOCKING THE POTENTIAL OF SMRs FOR DISTRICT HEATING: THE IMPORTANCE OF STAKEHOLDER ENGAGEMENT
126
ECONOMIC ASSESMENT OF THE DEPLOYMENT OF LOW-TEMPERATURE SMRs FOR DISTRICT HEATING IN EUROPE
127
CENTRALISED SPENT FUEL MANAGEMENT FOR HEAT-PRODUCING SMRs
128
FLOATING NUCLEAR POWER PLANTS: SITE AND SUPPORT FACILITY PLAN FOR THE NORDIC COUNTRIES
129
THE GEMINI+ SYSTEM for polygeneration of power, process heat and hydrogen
130
RECOMMENDATIONS TO ACCELERATE THE DEPLOYMENT OF FLOATING NUCLEAR POWER PLANTS, FROM A LICENSING APPROACH
131
ASVAD, A new safety element to avoid the complications of the undesired nitrogen injection to PWR reactors
132
STRATEGIC DEPLOYMENT OF LEAD-COOLED FAST REACTORS (LFRS) IN EUROPE: ADVANCING WASTE REDUCTION AND RADIOTOXICITY MANAGEMENT BY 2035
133
STAKEHOLDER ENGAGEMENT FOR A CENTRALIZED SPENT FUEL & WASTE MANAGEMENT FACILITY FOR LEAD-COOLED FAST REACTORS IN CONTINENTAL CENTRAL EUROPE
134
CENTRALIZED SPENT FUEL & WASTE MANAGEMENT FOR LFRs: SITE, INFRASTRUCTURE AND SUPPORTING FACILITIES
135
EVALUTION OF THE CONTENT OF RADIONUCLIDES IN FEED MIXTURES USED IN POULTRY FARMING
136
CENTRALIZED FACILITY FOR SPENT FUEL AND WASTE MANAGEMENT: A KEY ENABLER FOR LEAD-COOLED FAST REACTOR DEPLOYMENT IN EUROPE
137
SAFEGUARDS FOR CENTRALIZED FUEL & WASTE MANAGEMENT AND NUCLEAR FUEL TRANSPORT IN LFR REACTOR DEPLOYMENT
138
ANALYSIS OF NUCLEAR COMPONENTS INTEGRITY FOR LTO USING FAD
139
STUDY OF STRUCTURAL PROPERTIES IN POLYMERIC MATRIX WITH TUNGSTEN PARTICLES FILLER BY MEANS OF POSITRON ANNIHILATION LIFETIME SPECTROSCOPY
140
IMPROVED DESIGN OF GEMINI+ CORE, THE VERSITILE HTGR FOR POLIGENERATION
141
INTEGRATION OF SMRs INTO LOW-CARBON HYBRID ENERGY SYSTEMS: THE TANDEM EURATOM PROJECT AND BEYOND
142
RAPID SEPARATION AND DETERMINATION OF 55FE AND 63NI FOR DECOMMISSIONING AND NUCLEAR FORENSICS
143
RETHINKING NUCLEAR ENERGY INVESTMENTS: A LARGE TECHNOLOGICAL SYSTEM PERSPECTIVE
144
ORLEN SYNTHOS GREEN ENERGY SP. Z O.O. ACTIVITIES IN THE FRAME OF NUCLEAR SAFETY ASSESSMENT ON THE BWRX-300 POLISH LICENSING PATH
145
GEMINI 4.0 WP2: Conditions for decarbonization of European industry with nuclear polygeneration using High Temperature Reactors
146
HTGR–POLA AS THE FORERUNNER FOR HIGH TEMPERATURE NUCLEAR POLIGENERATION FOR INDUSTRY IN POLAND AND EUROPE
148
BULK HYDROGEN ANALYSIS USING NEUTRON REFLECTION FOR FOOD SAFETY
149
Imagining energy futures: societal perspectives on existing and emerging nuclear technologies
150
Reduced order modelling of the WWER-1000 reactor dynamics for fuel qualification
151
Project INERI Modeling of Small Modular Reactors with Accident Tolerant Fuels
152
Brittle fracture assessment for LTO of WWER RPV
153
ECOSENS - a European project on Economic and Social Considerations for the future of Nuclear Energy in Society
154
STUDY OF BETA DECAY OF FISSION PRODUCTS USING TOTAL ABSORPTION TECHNIQUE FOR DECAY HEAT CALCULATIONS
155
WOMEN IN NUCLEAR - THE ORGANISATION STRENGTHENING COOPERATION AND DEVELOPING THE COMPETENCE OF WOMEN WORKING IN THE NUCLEAR INDUSTRY
156
COMPARISON OF SELECTED ORGANIC COMPUNDS USED AS WORKING FLUID IN SECONDARY CIRCUIT IN NPP
157
COORDINATION OF THE EUROPEAN RESEARCH COMMUNITY ON NUCLEAR MATERIALS FOR ENERGY INNOVATION: THE RESEARCH AGENDA OF THE CONNECT-NM CO-FUNDED EUROPEAN PARTNERSHIP
158
OperaHPC: OPEn HPC theRmomechanical tools for the development of eAtf fuels: status at mid-project
159
THE HORIZON-EURATOM ESFR-SIMPLE PROJECT: MID-TERM ACHIEVMENTS
160
COAL-TO-NUCLEAR TRANSITION IN POLAND – AN ASSESSMENT OF NUCLEAR SAFETY ASPECTS
161
IMMOBILIZATION OF NUCLEAR WASTE IN CERAMICS AND GLASS MATERIALS: INCT EXPERIENCE AND FUTURE CHALLENGES
162
FROM CONCEPTION TO TECHNOLOGICAL IMPLEMENTATION - SMR`s TECHNOLOGY READINESS LEVELS
163
Radiological Inventory and Associated Activity Analyses Towards Decommissioning of a 40 MeV Medical Cyclotron VUB
164
DIRECT NUMERICAL SIMULATION OF TURBULENT FLOW AND HEAT TRANSPORT IN A TIGHTLY-SPACED ROD BUNDLE
165
NEURAL NETWORKS AND AI-DRIVEN DECISION MAKING FOR A MORE FLEXIBLE NUCLEAR INDUSTRY
166
DEEP LEARNING SURROGATE MODELS FOR NEUTRONIC IRRADIATION OPTIMISATION IN IFMIF-DONES
167
Computational dosimetry for improved worker radiation monitoring in neutron workplaces: Validation at Budapest Research Reactor
172
RADIATION AND ENVIRONMENTAL MONITORING OF THE TERRITORIES OF THE CHERNOBYL EXCLUSION ZONE – A KEY MOMENT IN ITS FUTURE DEVELOPMENT
173
GAMMA RADIATION SHIELDING GLASSES LENSES DESIGN IN GLASS MATERIAL SYSTEMS TeO2-TiO2-ZnO; WO3-MoO3-TeO2, AND Bi2O3-B2O3-TeO2
174
CONTINUOUS SIGNAL-BASED NEUTRON NOISE AND MULTIPLICITY MEASUREMENTS - A NUCLEAR INNOVATION AWARD WINNER
