TÍNH TOÁN HOẠT ĐỘ PHÓNG XẠ CỦA CÁC THÀNH PHẦN CẤU TRÚC LÒ PHẢN ỨNG HẠT NHÂN ĐÀ LẠT

TÍNH TOÁN HOẠT ĐỘ PHÓNG XẠ CỦA CÁC THÀNH PHẦN CẤU TRÚC LÒ PHẢN ỨNG HẠT NHÂN ĐÀ LẠT CHUẨN BỊ CHO KẾ HOẠCH D&D CURRENT STATUS CURRENT STATUS OF OPERATION AND UTILIZATION OF OF OPERATION AND UTILIZATION[.]

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CURRENT STATUS

OF OPERATION AND UTILIZATION OF

DALAT NUCLEAR RESEARCH

REACTOR AND 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

International Conference on Research Reactors:

Safe Management and Effective Utilization

16 – 20 November 2015, IAEA Headquarters, Vienna, Austria

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International Conference on Research Reactors: Safe Management and Effective Utilization

16 – 20 November 2015, Vienna, Austria

 Brief reactor description and its operation

 Main utilization of the DNRR

 Strategic plan for the next decade

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Contents

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Brief Reactor Description

and Its Operation

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4

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Ministry of Science and

Technology (MOST)

Vietnam Agency for Radiation and Nuclear Safety (VARANS)

Vietnam Atomic Energy Institute (VINATOM)

Scientific Council

Dept of International Relations Administration

(INST, Hanoi)

Institute for Nuclear Science and Technique

(INST, Hanoi)

Institute for Technology of Radioactive and Rare Element

(ITRRE, Hanoi)

Institute for Technology of Radioactive and Rare Element

(ITRRE, Hanoi)

Dalat Nuclear Research Institute (DNRI, Dalat)

Dalat Nuclear Research Institute

(DNRI, Dalat)

Center for Nuclear Technique

(CNT, HCMC)

Center for Nuclear Technique

(CNT, HCMC)

Research &

Development Center for Radiation Technology

(VINAGAMA, HCMC)

Research &

Development Center for Radiation Technology

(VINAGAMA, HCMC)

Center for Application

of NT in industry

(CANTI, Dalat)

Center for Application

of NT in industry

(CANTI, Dalat)

Center for Radiation Technology

(CRT, Hanoi)

Center for Radiation Technology

(CRT, Hanoi)

Center for NDE

(NDE, Hanoi)

Center for NDE

(NDE, Hanoi)

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History of the DNRR

 Early 1960: Started to construction of

former TRIGA Mark II Research Reactor

 02/1963: Achieved first criticality

fuel to USA

upgrading work of the TRIGA Mark II reactor (DNRR now)

 11/1983: Achieved first criticality with

VVR-M2 HEU fuel of 36% enrichment

500 kW

HEU FAs and 6 LEU FAs)

19.75% enrichment (full core conversion)

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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

Current core configuration

Fuel Assemly Beryllium

Control Rod Neutron Trap

Dry Irradiation Channel Wet Irradiation Channel

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Reactor Operation

Statistics of operation time of DNRR

Every 3-4 weeks, continuous runs of

130 hrs for RI production, NAA, basic

and applied researches, E&T, etc

Every 3-4 weeks, continuous runs of

130 hrs for RI production, NAA, basic

and applied researches, E&T, etc

The remaining time between two

consecutive runs for maintenance

activities and reactor experiments

The remaining time between two

consecutive runs for maintenance

activities and reactor experiments

Reactor control console

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

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Main Utilization of the DNRR

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 Main radioisotopes & radiopharmaceuticals researched and produced for medical purposes are:

- 131 I in Na 131 I solution and capsules

- Tc 99m generators in Sodium-( 99m Tc) pertechnetate

- 32 P applicator for skin disease therapeutics and

 Small sources: 60 Co, 192 Ir, etc.

RI and Radiopharmaceutical Production

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

Hot cell and I-131 production line

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Neutron Activation Analysis

was installed This system is used to analyze elements having short-lived nuclides with half-lives from 10  100 seconds.

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).

Fast pneumatic transfer system

Automatic sample changer system

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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 238 U, Fe, Al, Pb, 93 Nb, 12 C 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.

Neutron Beams Utilization

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The training courses using DNRR:

students from universities

The training program of this practical

course is aimed at complementing

theoretical lectures which the students

have learned at the universities.

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.

Education &Training

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.

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Strategic Plan

for the Next Decade

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 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.

Role of the DNRR in the National Policy Direction

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MISSION

The reactor will continue playing

an important role in nuclear sector in the country

MISSION

The reactor will continue playing

an important role in nuclear sector in the country

MAJOR OBJECTIVES

To continue operation of the DNRR

safely and reliably to at least 2025

MAJOR OBJECTIVES

To continue operation of the DNRR

safely and reliably to at least 2025 MAJOR OBJECTIVES

To improve the level of utilization in order to meet the needs of the society

 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

 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

SPECIFIC OBJECTIVES

 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

 Implement the effective programme for

ageing management of the reactor

 Perform periodic safety review for the

reactor in order to support for application

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Detailed Action Plans (1)

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

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to support for application of license renewal:

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

safety review of the DNRR will be conducted in years 2018-2022 comprising 4 phases:

(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

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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

based on quality assurance programme to the integrated

management system according to IAEA guidance

the effective ageing management for the DNRR

analysis report, operational limits and conditions, operating

procedures, the emergency plan and decommissioning plan, etc

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broaden researches on production of various

radioisotopes:

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

the reactor operation regime of 150 hrs/cycle will be applied and the facility upgrade for RI production will also be carried out

reactor will also be carried out through the implementation of

national research projects in the next few years

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on neutron activation and other related methods:

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

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

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reactor:

Among the activities using filtered neutron beams of the DNRR that will continue to be pursued are:

nuclear data, and continue to improve the precision and

sensitivity for PGNAA technique using the neutron beams

extracted through beam port of the reactor;

beams by developing neutron scattering and neutron radiography facilities

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and training:

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.

utilizing the DNRR

the operation and utilization of the new research reactor of CNEST

bilateral co-operation with international organizations for nuclear

education and training will continue to be promoted.

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 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

Concluding Remarks

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