CURRENT STATUS OF OPERATION AND UTILIZATION OF DALAT NUCLEAR RESEARCH REACTOR AND STRATEGIC PLAN

1. International Conference on Research Reactors: Safe Management and Effective Utilization 16 – 20 November 2015,IAEA Headquarters, Vienna, Austria CURRENT STATUS OF OPERATION AND UTILIZATION OF DALAT NUCLEAR RESEARCH REACTORAND STRATEGIC PLAN Luong Ba Vien and Nguyen Nhi Dien DALAT NUCLEAR RESEARCH INSTITUTE 01 Nguyen Tu Luc Str., Dalat, Vietnam Email: lbvien@hcm.vnn.vn

2. Contents • Brief reactor description and its operation • Main utilization of the DNRR • Strategic plan for the next decade • Concluding remarks

3. Brief Reactor Description and Its Operation

4. Ministry of Science and Technology (MOST) Vietnam Atomic Energy Agency (VAEA) Vietnam Agency for Radiation and Nuclear Safety (VARANS) Vietnam Atomic Energy Institute (VINATOM) Scientific Council Dept. of International Relations Dept. of Planning & R&D Management Administration Office The Organization Chart of VINATOM Nuclear Training Center (NTC Hanoi) Institute for Nuclear Science and Technique (INST, Hanoi) Institute for Technology of Radioactive and Rare Element (ITRRE, Hanoi) Center for Radiation Technology (CRT, Hanoi) Dalat Nuclear Research Institute (DNRI, Dalat) Center for Application of NT in industry (CANTI, Dalat) Center for Nuclear Technique (CNT, HCMC) Research & Development Center for Radiation Technology (VINAGAMA, HCMC) Center for NDE (NDE, Hanoi) 4 4 4

5. History of the DNRR • Early 1960: Started to construction of former TRIGA Mark II Research Reactor • 02/1963:Achieved first criticality • 3/1963: Operated at full power of 250 kW • 1968-1975: Shutdown • 1974-1975:Unloaded and shipped back fuel to USA • 03/1982: Started the reconstruction and upgrading work of the TRIGA Mark II reactor (DNRR now) • 11/1983: Achieved first criticality with VVR-M2 HEU fuel of 36% enrichment • 03/1984:Operated at nominal power of 500 kW • 09/2007:Operated with mixed core (98 HEU FAs and 6 LEU FAs) • 01/2012:Used only VVR-M2 LEU fuel of 19.75% enrichment (full core conversion)

6. Main Characteristics • Reactor type: Pool type (TRIGA Mark II, modified to Russian type of IVV-9) • Nominal power: 500 kW • Maximum thermal neutron flux in the core: 2.2x1013 n.cm-2.s-1 • Coolant and moderator:Light water • Reflector: Beryllium and graphite • Core cooling mechanism: Natural convection • Fuel type: Russian type, VVR-M2, dispersed UO2-Al, 19.75% enrichment • Control rods: 2 safety rods (B4C), • 4 shim rods (B4C) and 1 fine rod (SS) • Irradiation facilities: 1 central neutron trap, 2 pneumatic transfer channels, 1 wet vertical channel, 40 holes in rotary rack • Experimental facilities: 4 horizontal beam ports, and 1 thermal column Fuel Assemly Dry Irradiation Channel Wet Irradiation Channel Beryllium Control Rod Neutron Trap Current core configuration 6

7. Reactor Operation Reactor control console Every 3-4 weeks, continuous runs of 130 hrs for RI production, NAA, basic and applied researches, E&T, etc. Statistics of operation time of DNRR The total time of reactor operation from the beginning of 1984 to the end of 2014 is about 39,340 hrs, namely a yearly average of 1300 hrs, and the total energy released is about 787 MWd. • The remaining time between two consecutive runs for maintenance activities and reactor experiments.

8. Main Utilization of the DNRR

9. RI and Radiopharmaceutical Production • Main radioisotopes & radiopharmaceuticals researched and produced for medical purposes are: • - 131I in Na131I solution and capsules • - Tc99m generators in Sodium-(99mTc) pertechnetate • - 32P applicator for skin disease therapeutics and 32P in injectable solution • - 51Cr, 153Sm165Dy, etc. • - 15 types of labeled compounds using Tc99m , 131I 153Sm, etc. • Other radioactive tracers for sedimentology study, oil field study, and industry application can also be produced: 46Sc, 192Ir, 198Au, etc. • Small sources: 60Co, 192Ir, etc. Hot cell and I-131 production line In the last 5 years, about 400 Ci/year of radioisotopes are produced from the reactor and they are supplied to 25 nuclear medicine departments in the country. Each year, about 300,000 patients have been diagnosed and treated by radioisotopes produced at DNRI. RI products of DNRI

10. Neutron Activation Analysis • Different methods are used for element analysis at DNRI: • Instrumental NAA, including Ko-method • Radiochemical NAA • Prompt gamma NAA • Delayed NAA • In 2012, a fast pneumatic transfer system was installed. This system is used to analyze elements having short-lived nuclides with half-lives from 10  100 seconds. Fast pneumatic transfer system At the end of 2014, a total of about 60,000 samples have been irradiated at the reactor, giving a average of 2000 samples/year (60% of geological samples, 20% of environmental samples, 10% of biological samples, 7% of soil and agriculture materials, and 3% of industrial materials). Automatic sample changer system

11. Neutron Beams Utilization • Three out of four neutron beam ports (No.2, No.3 and No.4) are currently used for researches and applications. • Neutron physics and nuclear data measurement: • - Measurement of total neutron cross section for 238U, Fe, Al, Pb, 93Nb, 12C on filtered neutron beams at 24 keV, 54 keV, 59 keV, 133 keV, 148 keV and evaluation of average neutron resonance parameters from experimental data; • - Measurement of average neutron radioactive capture cross section of Re, V, W, Ag, Hf and In using filtered neutron beams extracted from the reactor; • - Development of the spectrometer of summation of amplitudes of coinciding pulses of (n, 2) reaction for nuclear structure data measurement. • Application of neutron capture gamma ray spectroscopy: • - Development of PGNAA technique using the filtered thermal neutron beam in combination with the Compton-suppressed spectrometer for analyzing Fe, Co, Ni, C in steel samples; Si, Ca, Fe, Al in cement samples; Gd, Sm, Nd in uranium ores, etc. • - Utilization of the PGNAA method for investigating the correlation between boron and tin concentrations in geological samples, analyzing boron in sediment and sand samples to complement reference data for such samples from rivers; • - Application of the spectrometer of summation of amplitudes of coinciding pulses of (n,2) reaction for measuring As and Se in biological samples.

12. Education &Training • The training courses using DNRR: • One-week practical training course for students from universities. • The training program of this practical courseis aimed at complementing theoretical lectures which the students have learned at the universities. • Two or three-week training course on reactor engineering for professionals (such as researchers, regulators, engineers, and teachers) • The training program of this course is to offer the knowledge of reactor engineering for the people who are involves in the national nuclear power programme. Experiment of approach to criticality DNRI has also participated in the education of PhD students and master students in the fields of nuclear physics, radio-chemistry, etc. In addition, DNRI has also established the bilateral co-operation with the JAEA and BARC of India in order to conduct various training courses in the nuclear field.

13. Strategic Plan for the Next Decade

14. Role of the DNRR in the National Policy Direction • On 3 January 2006, the Prime Minister signed a decision on launching the “Strategy for Peaceful Uses of Atomic Energy up to the year 2020”, which determines the objectives and road-map for atomic energy development in Viet Nam on both non-power and power applications. • According to this strategy the DNRI will participate in: • The project on establishment of a Center for Nuclear Science and Technology (CNEST) with a new 15-MW research reactor. • In connection with the project on the first NPP in Viet Nam, the DNRI will also participate in areas such as environmental monitoring and assessment, site survey, emergency planning, and public information.

15. MISSION The reactor will continue playing an important role in nuclear sector in the country MAJOR OBJECTIVES To improve the level of utilization in order to meet the needs of the society MAJOR OBJECTIVES To continue operation of the DNRR safely and reliably to at least 2025 • Increase the quantity of radioisotope production and broaden researches on production of various radioisotopes • Develop and complete the analytical techniques based on neutron activation and other related methods • Expand researches on filtered neutron beams of the reactor • Strengthen the use of reactor for education and training • Implement the effective programme for ageing management of the reactor • Perform periodic safety review for the reactor in order to support for application of license renewal • Enhance the quality management for the reactor • Update reactor safety documents SPECIFIC OBJECTIVES SPECIFIC OBJECTIVES

16. Detailed Action Plans (1) • Implement the effective programme for ageing management of the reactor: • To achieve this specific objective, the methodology used to detect and evaluate ageing degradation and countermeasures used for prevention and mitigation of ageing degradation will be continued to improve. • In addition to updating of the ageing management programme for the DNRR, other safety documents will also be updated to maintain their conformity with the actual status of the reactor.

17. Detailed Action Plans (2) • Perform periodic safety review for the reactor in order to support for application of license renewal: • After fulfillment of full core conversion from HEU to LEU fuels for the DNRR, the license for operation and utilization of the reactor with the validation of the 10-year duration was granted on 7 February 2013. • For the purpose of application of license renewal, the periodic safety review of the DNRR will be conducted in years 2018-2022 comprising 4 phases: • (1) Preparation of the PSR project (2018 -2019), • (2) Conduct of the PSR (2019-2021), • (3) Regulatory review (2019-2021) and • (4) Finalization of the integrated implementation plan (2020-2022). • The safety assessment of the reactor will be based on the safety factors as recommended in the IAEA Safety Guide.

18. Detailed Action Plans (3) • Enhance the quality management for the reactor: • Continue to improve and complete the existing quality assurance programme of the DNRR based on the annual assessment of the results of reactor operation and utilization, staff quality, completeness of safety documents, record keeping, etc. • Perform a gap analysis to move from the management system based on quality assurance programme to the integrated management system according to IAEA guidance. • Update the reactor safety documents: • This objective aims at ensuring safe operation and implementing the effective ageing management for the DNRR. • The updating will consist of such safety documents as safety analysis report, operational limits and conditions, operating procedures, the emergency plan and decommissioning plan, etc.

19. Detailed Action Plans (4) • Increase the quantity of radioisotope production and broaden researches on production of various radioisotopes: • The increase of the quantity up to about 550 Ci per year of radioisotopes and broadening of researches on production of various radioisotopes (such as Mo-99, Y-90, Ho-166, Lu-177 and Ir-192 ) will be a priority in the next ten years. • To achieve the objective of increasing the radioisotope quantity, the reactor operation regime of 150 hrs/cycle will be applied and the facility upgrade for RI production will also be carried out. • The research and production of various radioisotopes from the reactor will also be carried out through the implementation of national research projects in the next few years.

20. Detailed Action Plans (5) • Develop and complete the analytical techniques based on neutron activation and other related methods: • Development and completion of nuclear analytical techniques with and without use of reactor and related analytical techniques in order to offer a wide range of materials elemental analysis will continue to pay much attention at DNRI in the next ten years. • The continuing development of analytical methods such as cyclic NAA, epithermal NAA, k-zero method in prompt gamma neutron activation analysis (k0-PGNAA) and the improvement of automatization for NAA techniques will be one of the priority issues at the DNRI. These are being carried out under a ministerial research project during the years 2015-2017.

21. Detailed Action Plans (6) • Expand researches on extracted neutron beams of the reactor: • Among the activities using filtered neutron beams of the DNRR that will continue to be pursued are: • Continue to carry out the measurements for neutron physics and nuclear data, and continue to improve the precision and sensitivity for PGNAA technique using the neutron beams extracted through beam port of the reactor; • Expand the basic and applied researches on extracted neutron beams by developing neutron scattering and neutron radiography facilities.

22. Detailed Action Plans (7) • Strengthen the use of reactor for nuclear education and training: • In order to meet the rising demand in development of human resources for national nuclear power program, the DNRR will continue to play an important role in the nuclear education and training for students from universities and professionals with interest in reactor engineering. • In the next ten years, the DNRI will continue to offer training courses utilizing the DNRR. • The reactor will also be used for training staff who will participate in the operation and utilization of the new research reactor of CNEST. • Besides, the association with universities in the country and the bilateral co-operation with international organizations for nuclear education and training will continue to be promoted.

23. Concluding Remarks • More than 31 years of operation, the DNRR has played an important role in the use of atomic energy for peaceful purpose in Viet Nam. So far, the reactor has proved to be safe and reliable. • The reactor has been effectively used for radioisotope production for medicine and industry purposes; application of NAA in geological, crude oil and environment samples; performance of fundamental and applied researches on nuclear and reactor physics; as well as creation of a large amount of human resource with high skills and experiences on application of nuclear techniques in the country. • In order to join actively in the national strategy for peaceful uses of atomic energy and meet the demand of the society, a strategic plan for the DNRR in the next ten years has been set up to continue its safe operation and effective utilization at least to 2025. • After the year of 2025, as the high power research reactor puts into operation, the DNRR will change its utilization purpose and mainly use for NAA, basic researches, and education and training.

24. Thank you for your attention!