16 Innovative Nuclear Energy Research
 

This database contains 16 Research Reactors used for innovative nuclear research in 10 Member States.
Note that this view includes Reactors of the following status:
UNDER CONSTRUCTION, OPERATIONAL

Research reactors for development of materials and fuels for innovative nuclear energy systems.

see http://www.iaea.org/OurWork/ST/NE/NEFW/Technical-Areas/RRS/innovRnD.html

This search category presents the potential of extended utilization of RRs worldwide towards innovations in nuclear technologies. Data on research reactors currently involved in R&D for innovative nuclear energy projects or having certain potential for material and fuel testing research targeting deployment of innovative nuclear energy systems are documented as a Catalogue, which can serve for its users as assistant guide for planning R&D projects.

  1. OPERATIONAL RESEARCH REACTORS; OVERVIEW OF CURRENT CAPABILITIES FOR MATERIAL TESTING RESEARCH (MTR) - Table 1.pdf 
  2. PULSED RESEARCH REACTORS. OVERVIEW OF CAPABILITIES AND CAPACITIES - Table 2.pdf
  3. PLANNED RESEARCH REACTORS. OVERVIEW OF FUTURE CAPACITIES FOR MATERIAL TESTING RESEARCH - Table 3.pdf
  4. RESEARCH REACTORS WITH POTENTIAL FOR MATERIAL TESTING RESEARCH. OVERVIEW OF CAPABILITIES AND CAPACITIES - Table 4.pdf

Overview

Readers are encouraged to provide papers on their respective research reactors in order to be qualified for the RRDB category "Innovative nuclear energy research" as  "Reactors capable for materials and fuel testing research". These inputs should be prepared following the requested format as presented in the Catalogue annexes, and they will be included in the amended edition of the NE series report entitled "RESEARCH REACTORS FOR DEVELOPMENT OF MATERIALS AND FUELS FOR INNOVATIVE NUCLEAR ENERGY SYSTEMS"

 
Pagination :
CountryFacility NameTypeThermal Power (kW)Status
Russian Federation MBIR FAST, POWER150,000.000UNDER CONSTRUCTION
Belgium BR-2 TANK IN POOL100,000.000OPERATIONAL
Czech Republic LVR-15 REZ TANK WWR10,000.000OPERATIONAL
Czech Republic LR-0 POOL - VARIABLE CORE5.000OPERATIONAL
France ILL HEAVY WATER58,300.000OPERATIONAL
Hungary BUDAPEST RES. REACTOR TANK WWR10,000.000OPERATIONAL
Morocco MA-R1 TRIGA MARK II2,000.000OPERATIONAL
Netherlands HFR TANK IN POOL45,000.000OPERATIONAL
Norway HBWR HEAVY WATER20,000.000OPERATIONAL
Romania TRIGA II PITESTI - SS CORE TRIGA DUAL CORE14,000.000OPERATIONAL
Russian Federation MIR.M1 POOL/CHANNELS100,000.000OPERATIONAL
Russian Federation SM-3 PRESSURE VESSEL100,000.000OPERATIONAL
Russian Federation BOR-60 FAST BREEDER60,000.000OPERATIONAL
United States of America ATR TANK250,000.000OPERATIONAL
United States of America HFIR TANK85,000.000OPERATIONAL
United States of America UFTR UNIV. FLORIDA ARGONAUT100.000OPERATIONAL
Readers are encouraged to provide papers on their respective research reactors in order to be qualified for the RRDB category "Innovative nuclear energy research" as  "Reactors capable for materials and fuel testing research". These inputs should be prepared following the requested format as presented in the Catalogue annexes, and they will be included in the amended edition of the NE series report entitled "RESEARCH REACTORS FOR DEVELOPMENT OF MATERIALS AND FUELS FOR INNOVATIVE NUCLEAR ENERGY SYSTEMS".
 

Catalogue of RR capable for materials and fuel testing research

The users of the Catalogue (are national and international organizations directly involved in the development of materials and fuels for the nuclear energy industry which includes governmental and private sector organizations responsible for the development and/or deployment of innovative nuclear energy systems, designers, manufacturers, vendors, research institutions, safety authorities, technical support organizations, academia and some others. The Catalogue fosters wider access to existing RRs and thus ensures their increased utilization. The Catalogue can serve as a supporting tool for the establishment of regional and international networking through RR coalitions and International Centres based on Research Reactors (ICERR) Relative to material testing capabilities the research reactors presented in the Catalogue are categorized according to their:

  • current status (operational, planned or potential)
  • power level (high, medium, low),
  • mode of operation (steady state, pulsed),
  • neutron spectrum (thermal, fast),

Considered:

  • peculiar features provided (experimental volume combined with neutron flux)
  • ability to handle molten metals or salts or supercritical water,
  • in-situ instrumentation,
  • lifetime,
  • method of access.

Current status

  • Operational (Table 1Table 2)
  • Planned/ under construction (Table 3)
  • Potential Potentially able to step in material testing research (Table 4)

Reactors capable for materials and fuel testing research

Operational

Abstract: 
Oldest RRs (possibly with expected lifetime extension) MORE POWERFUL Material testing reactors (MTRs) IN USE
ReactorCountryPowerStart-up
LVR15Czech Republic10MW1957
HBWRNorway20MW1959
BR2Belgium100MW1961
SM-3Russian Federation100MW1961
HFRNetherlands45MW1963
HFIRUnited States of America85MW1965
OsirisFrance70MW1966
ATRUSA250MW1967
MIR.M1Russia100 MW1967
JMTRJapan50MW1968
BOR-60Russian Federation60MW1968


Research Reactors operating in steady state mode 

see Table 1 or Reactors below (Power categories)
High power RR (>=20 MW)
China, CARRCEFR
Egypt, ETRR-2
France, OSIRIS
India, DHRUVA
Indonesia, RSG-GAS
Japan, JMTRJOYO
Korea, HANARO
Netherlands, HFR
Norway, HBWR
Russia, SM-3BOR-60MIR.M1
USA, ATRHFIR
Belgium, BR-2,

Medium power (5 MW <= P < 20 MW)
Russia, RBT-6IVV-2M
Czech Republic, LVR-15
USA, MITR
Romania, TRIGA-PITESTI

Pulsed Research Reactors 

see Table 2 or Reactors below
Russia, BIGR
Kazakhstan, IGR
Romania, ACPR, TRIGA 
Awaiting input materials from:
Japan, NSRR
France, CABRI

Fast spectrum research reactors. Highest dpa rate (in steel 15-50 dpa/y)

Operating 
see Table 1 or Reactors below
Russia, BOR-60 
China, CEFR

Potential 
see Table 4 or Reactors below
Japan, JOYO 

Planned 
see Table 3 or Reactors below
Belgium, MYRRHA
France, ASTRID
Russia, MBIR 

Thermal spectrum Research Reactors providing high dpa (up to 15-25 dpa/y): 

see Table 1 or Reactors below
Russia SM-3  25 dpa/y in capsule-type experiments
USA, HFIR  14 dpa/y in capsule-type experiments
see Table 3 or Reactors below
France JHR (planned)   16 dpa/y in some dedicated loops 

Qualifying unique coolants for next generation reactors 

see Table 1 or Reactors below
BR-2  water loop PWR, liquid metal
OSIRIS  water loops PWR, BWR 
DHRUVA  water loop 1.6 MW, LWR
HBWR  water loops 200kW, BWR, PWR, VVER, CANDU
TRIGA-Pitesti  high  temperature water loop 100 kW, fuel testing
SM-3   high and low temperature water loops
MIR-M1  high temperature water/vapour/gas loops
ATR  high temperature water loops
see Table 3 or Reactors below
JHR (planned)   water loops PWR, BWR, VVER, Sodium(planned)

Specific experimental capabilities

see Table 1 or Reactors below
USA, ATR 
Belgium, BR2 
Norway, HBWR 
Russia, MIR.M1 
USA, HFIR

Method of access

Relative to primary mission and testing proposals
Bilateral agreements
Membership in a consortium
Scientific user facility
Different/particular modalities

 
Readers are encouraged to provide papers on their respective research reactors in order to be qualified for the RRDB category "Innovative nuclear energy research" as  "Reactors capable for materials and fuel testing research". These inputs should be prepared following the requested format as presented in the Catalogue annexes, and they will be included in the amended edition of the NE series report entitled "RESEARCH REACTORS FOR DEVELOPMENT OF MATERIALS AND FUELS FOR INNOVATIVE NUCLEAR ENERGY SYSTEMS".