Utilisation of the Dalat Research Reactor After Its …...Utilisation of the Dalat Research Reactor After Its Core Conversion Nguyen Nhi Dien et al. Dalat Nuclear Research Institute,

Utilisation of the Dalat Research Reactor After Its Core Conversion

Nguyen Nhi Dien et al.Dalat Nuclear Research Institute, VINATOM01, Nguyen Tu Luc Str., Dalat City, Vietnam

Joint IGORR 2014/ IAEA Technical Meeting, 17–21 November 2014, Bariloche, Argentina

Contents

Brie f description of the Dala t Nuclear Research Reactor (DNRR)

Recent projects re la ted to the DNRR

Utiliza tion of the DNRR afte r its core convers ion

Limita tions of the DNRR

Sta tus of a new RR project

Conclus ions

2

3

Brief description of the DalatNuclear Research Reactor (DNRR)

4

Layout of Dalat Nuclear Research Institute

North

South

EastWest

Reactor BuildingNuclear

Training Center

Building for radioactive

waste storage

Co-60 Irradiator Building

- Toa l a rea of 14.5 ha- 18 main buildings

and auxilia ry s tructures

- Main facilitie s : 500 kW RR, two Co-60

irradia tors of 16.5 KCi (1981) and 10

kCi (2007) respective ly

- Labs for research and deve lopment- Tra ining cente r.

5

History of the DNRR (1/2)

Early 1960 - Cons truction of the TRIGA Mark II reactor s ta rted

Feb. 26, 1963 - TRIGA reactor reached its firs t critica lity

Mar. 04, 1963 - The reactor was officia lly inaugura ted with the nomina l power of 250 kW

1963-1968 - The reactor had been opera ted with the 3 main purposes : training, research, and radioisotope production

1968-1975 - The TRIGA reactor was in extended shutdown

1974-1975 - Fuels were unloaded and shipped back to USA

March 15, 1982 - Project for recons truction and upgrading of the TRIGA Mark II (now DNRR) was s ta rted with Russ ian des ign.

6

History of the DNRR (2/2)

Nov. 01, 1983 - The DNRR reached its firs t critica lity with VVR-M2 HEU fue l of 36% enrichment

Mar. 20, 1984 - The reactor was officia lly inaugura ted with the nomina l power of 500 kW us ing 89 fue l assemblies

3/2002-9/2007 - 4 other re fue lings were done with the core working configuartions of 104 FAs and 106 FAs loaded

Sept. 12, 2007 - mixed core convers ion was success fully done with the core configura tion of 98 HEU and 6 LEU FAs .

2008 - Prepara tion works for full core convers ion were s ta rted

Nov. 30, 2011 - The reactor reached its firs t critica lity with 72 LEU VVR-M2 FAs of 19.75% enrichment

Since January 2012 - The reactor opera ted with the core working configura tion of 92 LEU FAs .

77

Main characteristics of the DNRRReactor type: Pool type (TRIGA Mark II, modified to Russ ian type of IVV-9)Nominal power: 500 kWtMaximum thermal neutron flux in the core: 2.1x1013 n.cm-2.s -1

Coolant and moderator: Light wate rReflector: Beryllium and graphiteCore cooling mechanism: Natura l convectionFuel type: Russ ian type , VVR-M2, UO2+Al, 19.75% enrichmentControl rods:

- 2 sa fe ty rods : B4C- 4 shim rods : B4C; 1 fine rod (SS)

Vertical irradiation channels: 4 holes in core and 40 holes a t the rota ry rackHorizontal beam-ports: 4 (1 tangentia l - No #3 and 3 radia l - No #1, #2, #4)Thermal column: 1

8

Once every 3-4 weeks , the DNRR is opera ted in continuous runs of 130 hrs for RI production, NAA, bas ic and applied researches , and educa tion and tra ining.

The remaining time be tween two consecutive runs is devoted to maintenance activities and a lso to reactor phys ics experiments .

Reactor operation

From 1984 to the end of 2014, the tota l opera tion time is about 39,000 hrs , namely a yearly average of 1200 hrs , and the tota l energy re leased was about 780 MWd.

9

Reactor utilization mainly for: Production of radioisotopes for medica l use and

other uses in indus try, agriculture , hydrology, scientific research, ...

Irradia tion of samples for neutron activa tion ana lys is (se rvice for geology, oil fie ld s tudy, environmenta l research, e tc.);

Neutron beam researches (PGNAA, NR, nuclear da ta measurement, e tc.); Tra ining of reactor opera tors , practica l works for

s tudents (from univers ities ); and Public information.

Officia ls of loca l authorities of Ninh Thuan Province

Beam ports No.4

1010

Reactor type

Nomina l thermal power Coolant and modera torReflectorFue l typeNumber of control rods

Neutron measuring channe lsVertica l irradia tion channe ls

Horizonta l beam-portsThermal columnUtiliza tion

TRIGA Mark II, modified to Russ ian type of IVV-9500 kW, s teady s ta teLight wate rBeryllium and GraphiteVVR-M2 UO2+Al, 19.75% enrichment7 (2 sa fe ty rods , 4 shim rods , 1 regula ting rod)3 (1 CFC and 1 CIC each)

4 (neutron trap, 1 wet channe l, 2 dry channe ls ) and 40 holes a t the rota ry rack4 (1 tangentia l, 3 radia l)1RI, NAA, PGNAA, NR, bas ic and applied researches , manpower tra ining

SUMMARY OF MAIN CHARACTERISTICS OF RR

11

Recent projects related to the DNRR

12

In the framework of the Reduced Enrichment for Research and Tes t Reactors (RERTR) Program and the Russ ian Research Reactor Fue l Re turn (RRRFR) Program, the DNRR core was necessary to be converted from Highly Enriched Uranium (HEU, 36% U-235) to Low Enriched Uranium (LEU, 19.75% U-235).

This 10-year project was s ta rted a t the beginning of 2004 and success fully finished a t the end of 2013.

Study on core des ign ca lcula tion, the rmo-hydraulics sa fe ty ana lys is , reactor phys ics and power res ta rt, e tc. have been done by DNRR staff in the collabora tion and support of Argonne Nationa l Labs (ANL), ROSATOM organiza tions and IAEA.

1. Conversion of reactor core from HEU to LEU fuel (1/6)

13

Utilization of HEU fuel before conversion of RR core in September 2007: The tota l number of HEU fue l assemblies (FA): 140 Fuel loaded in the core :

- 89 FA (1984 –4/1994)- 100 FA (89 irradia ted + 11 fresh) (4/1994 –3/2002)- 104 FA (100 irradia ted + 4 fresh) from March 2002- Re-shuffling 32 FA (16 by 16) in June 2004- 106 FA from November 2006- 34 unirradia ted FA in the s torage


Two s tages of core convers ion were planned: + Mixed-core (partly) convers ion: 2004 - 2007, and+ Full-core convers ion: 2008 - 2013

14


Fuel assembly VVR-M2 type :+ Tota l long: 865 mm+ Fue l mea t part long: 600 mm+ 3 layers (2 round tubes ins ide , 1 hexagona l outs ide)

Parameter HEU LEUEnrichment, % 36 19.75

Average mass of 235U in FA, g 40.20 49.70

Fuel meat composition U-Al Alloy UO2+Al

Uranium density, g/cm3 1.40 2.50

Cladding material Al alloy(SAV-1)

Al alloy(SAV-1)

Fuel element thickness (fuel meat and 2 cladding), mm

2.50 2.50

Fuel meat thickness, mm 0.70 0.94

Each cladding thickness, mm 0.90 0.78LEU fuel parameters

15

Main results of mixed-core convers ion which was ca rried out during 2004-2007:

Core ca lcula tion and sa fe ty ana lys is were done by DNRI’s s ta ffs in collabora tion with ANL.

36 fresh LEU FAs were supplied by Russ ian Federa tion in Sept. 2007.

35 fresh HEU FAs (34 s tandard and 01 Ins trumented) were sent back to Russ ian Federa tion NRI in Sept. 2007.

Mixed core of 98 FAs HEU and 6 FAs LEU was opera ted from September 2007.

Mixed core of 92 FAs HEU and 12 FAs LEU was opera ted from July 2009.


16

The full core convers ion from HEU to LEU was implemented during 2008 –2012.

Core des ign ca lcula tion and safe ty ana lys is were done by DNRI’s s ta ffs .

66 fresh LEU FAs were supplied by RF on Dec. 2010.

All HEU FAs in the reactor core were unloaded and moved to the spent fue l s torage in October 2011.

Reactor s ta rt-up with LEU fue l was done a t the end of November 2011 by DNRI’s s ta ffs .

Firs t critica lity achieved a t 15:35, 30 November 2011 with 72 LEU FAs .

LEU working core us ing 92 FAs es tablished on 14 December 2011.

106 spent HEU FAs were transported back to Russ ian Federa tion on 3 July 2013 .

1. Project for full-core conversion from HEU to LEU (5/6)

17

1. Project for full-core conversion from HEU to LEU (6/6)

Results of the ca lcula tion and reactor opera tion during the las t two years showed tha t the current working core met requirements not only sa fe ty but a lso utiliza tion.

Dependence of ra tio no/n on the number of FAs loaded into

the core .

Pos ition of control rods a t the critica l s ta te .

18

Origina l I&C sys tem of the DNRR was des igned and manufactured in the la te 1970s with ana log and low integra ted circuits . It was facing with age ing and obsolescence a fte r its ten-year opera tion from 1983-1992. The firs t renova tion was rea lized in 1992–1993 with the following works :

2. Renovation and modification of the reactor I&C system (1/2)

Reactor control console a fte r its firs t renovation

+ upgrading various e lectronic boards , blocks and sub-sys tems which mos t a ffect the re liability of sys tems+ replacement of the process and ins trumenta tion sys tem+ re -des ign of control console and control pane ls in the reactor control room. This project was supported under IAEA TC project VIE/4/010 and des igned, ins ta lled, tes ted and commiss ioned by DNRI’s ta ffs .

19

The second moderniza tion and re furbishment were ca rried out during 2005–2007 with the main purpose is replacement of the reactor control and protection sys tem including:+ neutron detector channels+ neutron measurement, data acquisition (Neutron Flux Control System -NFCS)+ reactor control and protection system+ control console+ control panels+ reactor protocol system+ etc.

2. Renovation and modification of the reactor I&C system (2/2)

Control console a fte r its second moderniza tion

This project was supported under IAEA TC VIE/4/014 and Nationa l projects and des igned, ins ta lled, tes ted and commiss ioned by DNRI’s ta ffs

New digita l I&C sys tem was commiss ioned in April 2007 and then it was licensed in October 2007.

20

Utilization of the DNRR

21

Main radioisotopes & radiopharmaceutica ls researched and produced for medica l purposes a re : - 131I in Na 131I solution and capsules- Tc99m genera tors in Sodium-(99mTc) pertechneta te- 32P applica tor for skin disease therapeutics and 32P in injectable solution - 153Sm, 186Re , 166Ho, 165Dy, 177Lu, e tc. - 15 types of labe led compounds us ing Tc99m , 131I 153Sm, e tc.

Other radioactive tracers for sedimentology s tudy, oil fie ld s tudy, and indus try applica tion can a lso be produced: 46Sc, 192Ir, 198Au, e tc.

Small sources : 60Co, 192Ir, e tc.

1. Radioisotope and Radiopharmaceutical Production (1/3)

RI products of DNRI

22


No. TYPE OF In-vivo KIT

01 Phosphontec02 Pyrotec03 Glucotec04 DMSA05 HIDA06 Phytec07 Citrate08 MAA 09 HM-PAO10 MIBI11 MAG-312 MDP13 EDTMP14 DISIDA15 ECD

23


Sta tus of radioisotope production for medica l use

Each year about 250 Ci of radioisotopes a re produced from the reactor and they a re supplied to 25 nuclear medicine departments in the country. About 3000 bottles of in-vivo kit a re produced us ing for diagnos is and therapeutics for about 300 thousands of pa tients in a year. Due to limita tion of power and irradia tion facilitie s , RI products from DNRR don’t mee t the demand of end-users .

Under FNCA program, the PZC based technology for production of 99mTc- genera tor has been s tudied a t DNRR. ZrMo, TiMo and PZC based genera tor could play an important role as a lte rna tive technology for production of 99Mo/99mTc genera tor from reaction 98Mo(n, –)99Mo. However, these methods were not very appropria te for the low power research reactor as DNRR.

24

2. Neutron Beams Researchesand Applications (1/4)

Horizonta l section view of DNRR

Beam port # 1

Beam port # 2 Beam port # 3

Beam port # 4

Core

Thermalizing column (closed)

ThermalColumn

Pool tank wall

Spent fuel storage tank

Concreteshielding

Graphite reflector

doorColumn

Bellowsassembly

Stainless steel

Aluminum

LN Dewar

HPGe

HPGe

PGNAA Sys tem

SACP Sys tem

Control table

PTS Sys tem

Horizonta l irradia tion channe ls and thermal neutron flux: n.cm-2.s -1

+ Tangentia l beam port No. 3: 2.3x106

+ Radia l beam port No. 4: 1.8x107

+ Radia l beam ports No. 2: spectrometry sys tem with BGO de tectors .

+ Radia l beam ports No. 1: not used ye t

+ Thermal column: 5.8x109

25


At present, three of four neutron beam ports a t the reactor (No #2, No #3 and No #4) a re used.

Neutron filte rs have been ins ta lled in beam ports to extract neutron beams from the reactor.

Based on these filte rs , thermal and quas i-monoenerge ticneutrons (24 keV, 54 keV, 59 keV, 148 keV, e tc.) have been used for nuclear da ta measurements , PGNAA, irradia tion of e lectronic components and other purposes (n,γ; n,2γ; n,n’ reactions ).

Thermal column has been used for neutron activa tion ana lys is of short-lived radioisotopes us ing the fas t pneumatic trans fer sys tem.

26

Beam port No #2: a HPGe-BGOgamma-rays Compton suppress ion spectrometer has been ins ta lled for PGNAA and experiments on neutron capture reactions . Beam port No #3: a γ-γ coincidence

spectrometer used an opposed couple of HPGe detectors has been developed for nuclear energy leve l and nuclear leve l dens ity measurements . Beam port No #4: a HPGe spectrometer,

and He-3 and Proton-recoil counters have been ins ta lled for nuclear da ta measurements of neutron tota l and radioactive capture cross sections .


Beam ports No #2 (above) and No #4 (be low)

27

High precis ion measurements of tota l and partia l cross sectionsfor fundamenta l neutron-nuclear inves tiga tions .

Measurements of neutron capture gamma-spectra . Measurements of activa tion cross sections . Isomeric ra tio inves tiga tions . Inves tiga tions of Dopple r-e ffect. Research of radia tion damage energy dependence in materia ls . Neutron radiography and tomography. Boron-Neutron Capture Therapy (BNCT). Prompt Gamma-ray Activa tion Analys is (PGAA). Development of s tandard fluxes for neutron-dos imetry purposes . Energy ca libra tion of proton recoil counte rs .


Summary of the main applications of mono-energetic neutron beams at DNRR:

28

3. Neutron activation analysis (1/3)

Different methods deve loped and used for e lement ana lys is :–Ins trumenta l NAA, including Ko-

method–Radiochemica l NAA–Prompt gamma NAA–Delayed NAA

K-zero method for INAA has been developed to ana lyse a irborne particula te samples for inves tiga tion of a ir pollution; crude oil samples and base rock samples for oil fie ld s tudy

A fas t pneumatic trans fer sys tem was ins ta lled in 2012. This sys tem is used to ana lyze e lements having short-lived radioisotopes such as F, Se , –Fas t pneumatic trans fe r sys tem

a t ce ll 13-2 and thermal column

Pneumatic trans fe r sys tem a t ce ll 7-1

29

3. Neutron activation analysis (2/3)

Automatic sample changer sys tem

At the end of 2014, a tota l of about 30,000 samples have been irradia ted a t the reactor, giving a yearly average of 1000 samples .

At present: - To do services for various purposes

(geology exploration, oil prospecting, agriculture, biology, environmental studies, etc.).

- QA/QC management for analytical laboratories is being set up and implemented in the framework of RCA project and national projects.

30

3. Neutron activation analysis (3/3)Main applica tions of NAA us ing the DNRR: Acquis ition of base line da ta for toxic e lement in environment; Research

& monitoring on a ir & marine pollution Determina tion of trace e lements in plants used in traditiona l medicine Determina tion of concentra tion & dis tribution of minera ls in food; Heavy

meta l and toxic e lements in foods tuffs Determina tion of Hg, Me-Hg and Se in human head ha ir Supporting the deve lopment of agriculture & improving the human life

qua lity Determina tion of multi-e lements in geologica l samples for minera l

explora tion Determina tion of U, Th, K & trace e lements in crude oil & base rock

samples Class ifica tion and provenance of a rte facts for s tudy on a rchaeology Analys is of e lements (off-line) and ava ilability to check of process (on-

line on conveyor) in indus try Providing ana lytica l se rvices to cus tomers of various fie lds e tc.

31

4. Gemstone-Coloring Study (1/3)

Color-enhancing methods have been done:

Gamma irradia tion by Co-60 irradia tors ; Neutron irradia tion combining with gamma irradia tion; Irradia tion combining with hea t trea tment; Heating

Irradia tion facilities in the reactor

Irradia tion pos ition Thermal neutron flux (n/cm2/s )

Es timated fas t neutron flux

(n/cm2/s )

Vertica l (wet) channe l a t ce ll 1-4 in the reactor core

1.2 × 1013 1.0 × 1013

Rota ry specimen rack in the beryllium re flector

4.2 × 1012 4.5 × 1012

Radia l horizonta l beam tube No. #4

2.1 × 107 (*) 5.0 × 109 (**)

32


Conta iner Dimens ion:

Results:

- Diameter: 28 mm

- Length: 200 mm

- Cadmium layer thickness : 0.5 mm

Limita tion of our reactor: low power and a few in-core irradia tion holes , difficulty of

beam tube utiliza tion No commercia l work can be conducted a t RR a t this moment.

33


Decay time afte r irradia tion:

Cooling time after gemstone irradiation

0

1020

3040

5060

70

8090

100110

120

1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16

MonthNu

mber

of sa

mple

- Afte r 6 months : about 80% re leased

- Afte r 16 months : 100% re leased

- 4 main radioisotopes activa ted: Sc-46 (T1/2 = 83.8 d), Ta-182 (T1/2 = 115 d), Sb-124 (T1/2 = 60.2 d), and Cs-134 (T1/2 = 753 d).

- Advantages in neutron irradia tion: Shorte r irradia tion time compared with others and permanent crea ted color- Disadvantages in neutron irradia tion: long cooling time (6-16 months ) due to high radioactivity leve l- Color a ttracted by traders a t current moment: pink and citrine quartz; Blue topaz.

34

5. Education &Training (1/4)

Tra ining Cente r of the DNRI was es tablished in 1999 in order to tra in and educa te s ta ffs VINATOM and people working in other ins titutions in the fie ld of nuclear energy and applica tion of nuclear techniques .

Tra ining courses have been organizing a t Tra ining Cente rincluding: reactor engineering, reactor opera tion, radia tion protection, radioactive was te management, applica tion of nuclear techniques and radioisotopes in indus try, agriculture , biology and environment, e tc.

Tra ining Center Building

35


Tra ining courses us ing the reactor include :

- One-week (or two weeks) practica l tra ining course for s tudents from the univers ities in the country (HoChiMinh City Univers ity of Science , Hanoi Univers ity of Science , Electric Power Univers ity, Univers ity of Dala t, e tc).

- Three-week tra ining course on reactor engineering for profess ionals (s ta rted in 2008 in coopera tion with JAEA; certifica ted about 120 participants from VINATOM, VARANS, VAEA, EVN and Univers ities in the country).

S tudents from Electric Power Univers ity

The 1s t JTC on Reactor Engineering

36


Main subjects of the practica l tra ining course a re :

Introduction to the DNRR and its technologica l sys tems; Introduction to reactor ca lcula tions us ing MVPand SRAC computer codes ; Introduction to the sa fe ty ana lys is for the DNRR; Introduction to the radia tion protection and was te management a t the DNRI; Computer code /experimenta l exercises : MVPand SRAC codes , gamma radia tion shie lding, measurement of gamma dose versus dis tance , reactor opera tion, approach to critica lity, control rod ca libra tion, and measurement of neutron flux; Vis it of the DNRR facilitie s .

Students with introductory lectures

Measurement of neutron flux

37


Main topics of the reactor engineering course a re :

Introduction to nuclear reactors : Overview of PWR/BWR, Research reactor Reactor phys ics and thermal hydraulics : Reactor phys ics , Reactor kine tics , Reactor hea t removal Fuel/mate ria l bas ic property of fue l: S tructura l mechanics , Materia l engineering, Fue l engineering Radia tion protection/radioactive was te management: Overview of hea lth phys ics , Radia tion shie lding, Radioactive was te management Safe ty ana lys is : Introduction to reactor sa fe ty, RIA, LOCA, PSA Computer code /experimenta l exercises : Reactor s imula tion, MVP/SRAC/COOLOD/EUREKA/ORIGEN/ORION-WIN code exercises , Experimenta l exercises on approach to critica lity, control rod ca libra tion, and measurement of thermal neutron flux in the reactor core Technica l vis it: Vis it of the DNRR facilitie s .

38

Limitations of the DNRR

+ Low power leve l:- long run continuous ly for RI no benefit in economy view-point.- imposs ible to produce long-lived RIs : Y-90, Mo-99, I-125, Xe-133, C-14, S-35, Co-60, Sm-153, Ir-192, e tc.

+ Low power leve l and limita tion of irradia tion facilitie s :- imposs ible to mee t the demands of medica l uses of the country- difficult to se rve for indus try applica tions and other reques ts .

+ Low neutron flux a t horizonta l channe ls : - limita tion for s tudy on mate ria l science with neutron sca tte ring.

+ Age of reactor is more than 50 years Aging problem.

However, the Dalat reactor is suitable for NAA, education & training for HRD and some fundamental researches on nuclear physics.

39

Status of a New RR Project

40

Educa tion and tra ining (E&T) for the na tiona l nuclear power program.

CNEST

Technica l support for the na tiona l nuclear power program (ensuring sa fe and economica l opera tion of NPPs).

Advanced researches in the a rea of a tomic energy.

Applica tion of nuclear techniques , radia tion technology; production of isotopes , s ilicon doping, e tc.

Main functions of the CNEST:

A new Center for Nuclear Energy Science and Technology (CNEST) with a new RR will be established

41

Proposed Structure of CNEST

VINATOM

CNEST

Basic NuclearResearch

ReactorEngineering

NuclearSafety

Radwaste, Rad.Protection,

Env. Monitoring

MaterialScience

BiologicalScience

RadioisotopeProduction

Nucl. Electronic& Computer Sc.

NuclearTraining

ResearchReactor

Red – related to nuclear power

42

Expectation of the new RR utilization

Radioisotope production;

Neutron activa tion ana lys is ;

Neutron beam applica tions (mate ria l science , neutron radiography, e tc.);

Materia l transmuta tion (S ilicon doping, gemstone colora tion, e tc.);

Materia l irradia tion for NPP projects ;

BNCT- Boron neutron capture therapy;

Human resources deve lopment;

Others .

The CNEST may have a significant contribution in the development of sustainable nuclear power program for Vietnam.

43

CNEST project: Key milestones (1/3)

November 2011: Inte rGovernment Agreement (IGA) be tween Vie tnam and Russ ian Federa tion s igned

2011 - 2013: S tudy and eva lua tion of the s ite for the new Research Reactor (RR)

2013: S tra tegic a reas for R&D, de te rmina tion of the main components of the CNEST

2014: Comple tion of the Terms of Reference (TOR –or technica l task) for FS

April 2014: Proposed site in Lam-dong Province for FS has been selected by the Government.

44


May 2014: Pre liminary survey of the proposed s ite was ca rried out by the experts of Rosa tom, Vina tom, and loca l Organiza tions of Lam-dong Province .

Survey results concluded tha t in technica l point of view the proposed s ite has some disadvantages :

land space for ins ta lla tion of reactor building, RI building and building for pos t-irradia ted mate ria l te s t is long enough but too narrow;

it was too fa r from the centre of Dala t city, e tc.

Two other s ites in Dong-na i Province have been proposed for survey and se lection.

FS may be started from the Middle of 2015.

Following IAEA Guidelines NP-T-5.1:

PHASE 3Implementation

PHASE 1 Pre-project PHASE 2Project Formulation

5 – 10 years

Pre-Project Assessment Report and Preliminary

Strategic Plan

Preparatory work for aresearch reactor after a policydecision has been taken

Implementation of a research reactor

Operations

Feasibility Study

Bid Specification

CommissioningLicence

ResearchReactor Justification

INFRASTRUCTURE MILESTONE 1

Ready to make a knowledgeable

commitment to a Research Reactor

project

Continuous development of infrastructure elements,Ongoing research reactor technology assessment & fuel cycle assessment

DecommissioningLicense

Research Reactor

Decomm-issioning


Ready to invite bids for a Research Reactor


Ready to commission and operate the

Research Reactor

Considerations before a decision to launch a research reactor project is taken

Possibility of a research

reactorconsidered

Rese

arch

Rea

ctor

Pr

ojec

t

Infr

astr

uctu

re D

evel

opm

ent

Prog

ram

Justification for

Research Reactor

2010 2014 2021 - 2022 ? 45


46

During more than 30 years of opera tion, the DNRR has played an important role in the use of a tomic energy for peaceful purpose in Vie tnam.

The reactor has been utilized to: Produce radioisotopes for medicine and indus try use , Carry out NAA of geologica l, crude oil and environment

samples , Carry out fundamenta l and applied researches on

nuclear and reactor phys ics , Crea te a la rge amount of human resource with high

skills and experiences on applica tion of nuclear techniques in the country.

Conclusions (1/2)

47

However, due to the limita tion of power leve l, irradia tion facilitie s and the age ing of the reactor facilitie s , the exis ting reactor can not mee t the increas ing user’s demands .

Requirement of building a new multi-purpose research reactor with power leve l of about 15 MW is essentia l to increase nuclear potentia l of the country, to meet the demands of energy and non-energy re la ted applica tions .

The main role of a new research reactor is to se rve the nuclear power deve lopment program, to promote the applica tion of nuclear science and technology, and to tra in scientific and opera tiona l s ta ff for the nuclear sector in the future .

Conclusions (2/2)

Thank you for your attention!

Documents

Utilisation of the Dalat Research Reactor After Its …...Utilisation of the Dalat Research Reactor After Its Core Conversion Nguyen Nhi Dien et al. Dalat Nuclear Research Institute,