Safety of Experimental Facility in JRR-3

1. Safety of Experimental Facility in JRR-3 Regional Workshop on the Application of the Code of the Conduct on the Safety Research Reactors 22 - 27 September 2013 in Yogyakarta, Indonesia H. Horiguchi Japan Atomic Energy Agency

2. Contents • Description of JRR-3 • Safety of experimental facility • Safety regulation in Japan • Safety assessment system in JAEA • Conclusions Japan Atomic Energy Agency

3. Japanese Research Reactors 14 8 9 22 As of September 2012 × Japan Atomic Energy Agency

4. Nuclear Science Research Institute ( NSRI ) J-PARC NSRR JRR-3 JRR-4 Japan Atomic Energy Agency

5. Overview of JRR-3 • History • First critical : 12th September, 1962 • Upgrade : 22nd September, 1990 • Basic characteristics of JRR-3 • Max. thermal power : 20MW • Reactor type: pool type • Coolant and moderator: Light water • Fuel type: Silicide fuel with low enriched uranium • Operation : 26 days / cycle • : 7 cycle / year • Main Purpose • Beam Experiment • Irradiation test • Activation analysis • RI production • Silicon semiconductor production Reactor Pool CNS Vertical Irradiation tube Heavy water tank Reactor core Japan Atomic Energy Agency

6. Fuel Element of JRR-3 • Fuel characteristics • Silicide with burnable poison (Cadmium) • Enrichment : 20 % EU = LEU • Number of fuel plate: 21 plate (standard) • :17 plate (follower) • Refueling • Burn up ratio of refueling: 55 % • Upper limit of BU: 60 % • Calculation code: SRAC code system • Average number of refueling: • 2 elements / cycle

7. Experimental facilityof JRR-3 9C Irradiation facilities • VT, RG, BR, SH Tube • Capsule irradiation & RI production • HR • Hydraulic transfer facility for RI production & NAA • PN • Pneumatic transfer facility for RI production & NAA • PN3 • Pneumatic irradiation facility for NAA • SI Tube • Irradiation facility for NTD of silicon • DR Tube • Rotating irradiation facility 8T 1G 2G CNS SI PN-3 HR-1,2 3G SH PN-1,2 DR 4G Horizontal tubes • 1G – 6G : Neutron scattering experimental facility • 7R : Neutron radiography facility • 8T, 9C : Neutron beam facility with mirror guide 5G 7R 6G Irradiation facility Japan Atomic Energy Agency

8. CNS Vacuum chamber Mirror guide Heavy Water tank Experimental facility Liquid H2 Moderator cell Cold neutron Thermal neutron • CNS convers thermal neutrons to cold neutron with liquid hydrogen for neutron beam facility. • CNS equipment: Moderator cell, Condenser etc. • Helium refrigerator system: Helium compressor, storage tank etc. Japan Atomic Energy Agency

9. Neutron beam Experiment Reactor building Experimental building Japan Atomic Energy Agency

10. Limiting conditions for operating • Operation of experimental facilities is carried out in accordance with the operational safety program approved by the regulatory body. • The limitations of experimental facility such as reactivity and heating of irradiation material are established in order to protect the reactor and irradiation sample. • If the limitations should not be complied, regulatory body could order to suspend the operation of research reactor. Therefore, compliance of the LCO is very important for the operating organization to use the experimental facility. Japan Atomic Energy Agency

11. Implementation of the code of conduct on modification and utilization 1. Assessment and verification of safety (code paragraph 22a) 2. Assessment of modification for experiment (code paragraph 32g) 3. Establishment of safety review committee (code paragraph 32h) 4. Assessment and approval of modification (code paragraph 32i) Japan Atomic Energy Agency

12. Flow of Safety Regulation for Research Reactor By Nuclear regulation authority (NRA) Planning and design phase • Licensingfor reactor installation • Approvalfor design and method of construction Construction phase Modification - Inspection of pre-service • Approval for design and method of construction Operation and Utilization phase • Approval for operational safety program • Periodical safety inspection (once a quarter) • Periodical hardware inspection (once a year) • Periodic safety review (every 10 years) etc. Decommissioning phase - Approval for the plan of decommissioning Japan Atomic Energy Agency

13. Legislations for RR of Japan Atomic Energy Basic Law Law for the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactor ( Reactor Regulation Law ) Rules for technical criteria for Method for Design and Construction of RR Rules for technical criteria for weld of RR Rules for Installation, operation, etc. of RR Japan Atomic Energy Agency

14. New Regulatory System of Japan New Regulatory System Old Regulatory System Ministry of Education, Culture, Sports, Science and Technology ( MEXT ) Cabinet Office Nuclear Regulation Authority ( NRA ) Atomic Energy Commission of Japan Ministry of the Environment • Safety regulation for test and research reactor • Safeguards • Regulations on the use of radioactive isotopes Nuclear Safety Commission of Japan Secretariat of the Nuclear Regulation Authority Regulation by Double Check 19 Sep, 2012 Regulation Regulation Research institutes, universities, etc. Electric utilities, Research institutes, universities, etc. Japan Atomic Energy Agency

15. Safety regulation on planning and design phase • Safety regulation of planning and design phase • In the safety regulation of RR, a two step approach is taken to start construction of reactor, such as licensing for reactor installationand approval of design and method of construction. • The experimental facility should be the design which does not influence the safety of reactor. • Licensing for reactor installation • Approval for design and method of construction Japan Atomic Energy Agency

16. Safety regulation on planning and design phase • Licensing for reactor installation • The operating organization submits an application for permit of reactor establishment to NRA in accordance with the Reactor Regulation Law. • The application documents consist of a Main body and Attachments including descriptions on safety design of the RR, experimental facility, radiation control ,and incidents and accidents. • Approval ofdesign and method of construction • The operating organization submits a design and method of construction to obtain an approval of NRA. (submissions are separable for equipment units) • After obtaining an approval of the design and method of construction, the operating organization starts construction. Japan Atomic Energy Agency

17. Safety regulation on construction phase • Pre-Service Inspection • During construction, the operating organization undergoes Pre-Service Inspection. • In the Pre-service Inspection, NRA confirms that the construction is conducted in accordance with the design and method of construction and technical standard. Japan Atomic Energy Agency

18. Safety regulation on operation phase • Approval of Operational Safety Program • The operating organization must receive approval for the operational safety program prior to the start of operation of the research reactor. • The operational safety program describes fundamental matters for operating the research reactor safely. • Inspection • Periodical safety inspection in accordance with the approved operational safety program. [once a quarter] • Periodical hardware inspection. [once a year] Japan Atomic Energy Agency

19. Safety Assessment system in JAEA-Tokai Director general Chief Engineer of Reactor Reactor Safety Review Committee QA Committee Department Radiation Protection etc. Research Reactor Operational safety administration Safety Review Committee Division RR Technology management RR Utilization RR Operation Irradiation facility management Utilization users desk Experiment device management CNS management

20. Safety Assessment system in JAEA • Safety review committee in JAEA • Reactor safety review committee under the director general • Safety review committee under the department director • Main subjects of safety review committee • Safety matter related to the installation, modification and repair of Reactor and utilization facility • Safety matters related to the design of irradiation capsule • Establish or revision of the operational safety program and operation manual • Safety matters related to setting or lifting of the radiation controlled area etc. Japan Atomic Energy Agency

21. Procedure of safety assessment in JAEA Quality assurance is applied at all stages in the design management that is planning, the safety review, construction and inspection. Establish of design management plan Clarification of design requirements Decision of basic design • Cont. of safety Analysis • [Case of PN-3] • Pressure resistance analysis • Radiation resistance analysis • Heat-resistance analysis • Seismic assessment Safety analysis of detailed design Comparison ofdesign requirement and design specification Deliberation & Suggestion Safety review committee meeting Decision of design specification • Cont. of inspection • [Case of PN-3] • Material inspection • Visual test / Dimensional check • Pressure resisting inspection Construction Making of pre-service inspection manual Pre-service inspection

22. Conclusions • Compliance of the LCO is very important for the operating organization to use the experimental facility safely. • Operating organization must take the primary responsibility to ensure the safety of the experimental facility by the self-controlled safety management system. • Our practices indicate that our safety activities for the experimental facilities meet safety requirements of the Code. Japan Atomic Energy Agency

23. Thank you for your attention! Japan Atomic Energy Agency