Safety of Experimental Facility in JRR-3
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1 Safety of Experimental Facility in JRR-3 Regional Workshop on the Application of the Code of the Conduct on the Safety Research Reactors September 2013 in Yogyakarta, Indonesia H. Horiguchi
2 Contents 1. Description of JRR-3 2. Safety of experimental facility - Safety regulation in Japan - Safety assessment system in JAEA 3. Conclusions
3 Japanese Research Reactors As of September 2012
4 Nuclear Science Research Institute ( NSRI ) NSRR J-PARC JRR-3 JRR-4
5 Overview of JRR-3 CNS Reactor core Reactor Pool Vertical Irradiation tube Heavy water tank History - First critical : 12 th September, Upgrade : 22 nd 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
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 facility of JRR-3 Irradiation facilities 9C 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 3G 2G 1G PN-1,2 SI CNS DR PN-3 HR-1,2 SH 8T Horizontal tubes 4G 1G 6G : Neutron scattering experimental facility 7R : Neutron radiography facility 8T, 9C : Neutron beam facility with mirror guide 5G 6G 7R Irradiation facility
8 CNS Vacuum chamber Liquid H 2 Heavy Water tank Mirror guide Experimental facility Moderator cell Thermal neutron Cold 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.
9 Neutron beam Experiment Reactor building Experimental building
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.
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)
12 Flow of Safety Regulation for Research Reactor Planning and design phase - Licensing for reactor installation - Approval for design and method of construction By Nuclear regulation authority (NRA) Construction phase - Inspection of pre-service Modification - 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
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 weld of RR Rules for technical criteria for Method for Design and Construction of RR Rules for Installation, operation, etc. of RR
14 New Regulatory System of Japan Old Regulatory System New Regulatory System Cabinet Office Atomic Energy Commission of Japan Ministry of Education, Culture, Sports, Science and Technology ( MEXT ) Nuclear Regulation Authority ( NRA ) Ministry of the Environment Nuclear Safety Commission of Japan Regulation by Double Check Regulation Safety regulation for test and research reactor Safeguards Regulations on the use of radioactive isotopes Regulation Secretariat of the Nuclear Regulation Authority 19 Sep, 2012 Research institutes, universities, etc. Electric utilities, Research institutes, universities, etc.
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 installation and 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
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 of design 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.
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.
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]
19 Safety Assessment system in JAEA-Tokai Director general Reactor Safety Review Committee Chief Engineer of Reactor QA Committee Department Radiation Protection etc. Safety Review Committee Research Reactor Operational safety administration Division RR Operation RR Utilization RR Technology management Utilization users desk Irradiation facility management 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.
21 Procedure of safety assessment in JAEA Design Management Establish of design management plan Clarification of design requirements Proponent Decision of basic design Quality assurance is applied at all stages in the design management that is planning, the safety review, construction and inspection. Comparison of design requirement and design specification Safety review committee meeting Safety analysis of detailed design Deliberation & Suggestion Cont. of safety Analysis [Case of PN-3] Pressure resistance analysis Radiation resistance analysis Heat-resistance analysis Seismic assessment Construction Pre-service inspection Decision of design specification Making of pre-service inspection manual Cont. of inspection [Case of PN-3] Material inspection Visual test / Dimensional check Pressure resisting 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.
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