Report of
FNCA 2008 Workshop on
The Utilization of Research Reactors

Following the agreement at the Ninth Coordinators Meeting 2008 in Tokyo, Japan, the FNCA 2008 Workshop on The Utilization Of Research Reactor took place as follows;

2008 FNCA Workshop on The Utilization Of Research Reactor was held at Vietnam, Dalat. This event consisted of 2 workshops on sub-projects, namely Neutron Activation Analysis (NAA) and Research Reactor Technology (RRT). The activities of both 2 projects are supposed to be performed for 3 years including this first year. Besides, FNCA open seminar co-hosted by 2 projects was held during the workshops as usual. The participants in the workshops gave the special lectures on the utilization of research reactor, the current status of nuclear power plant and so on.

Neutron Activation Analysis (NAA) Workshop was held for 5 days on October 16 - 19, 2008 and participated by 15 representatives from 10 FNCA member countries, namely Australia, Bangladesh, China, Indonesia, Japan, Korea, Malaysia, The Philippines, Thailand and Vietnam.
Neutron Activation Analysis is an elements analysis method by measuring the radioactivity and energy of activated elements in the sample irradiated by neutron beam. This method has an excellent beauty that is able to analyze all elements in the sample at once. The project is going to perform the activities for the promotion of utilization on 3 themes that may be expected to make great socio-economic contribution over the next 3 years. In the workshop, participants exchanged several information about the current status of radiometric analysis activities and the research reactor of each country. And they discussed .the choice of themes they could be engaged in, Implementation plans, objectives and so on.

Themes and contents are as follows;

Initial indication of participation : Australia [Leading country], Japan, (In the process of registration) This activity has a plan to grasp “the resources” recognized as the urgent need for mankind with mapping the distribution of elements on the land surface. Participants are expected to discuss and collaborate with the authorities concerned and promote the prevalence of Neutron Activation Analysis.

Initial indication of participation : China, Korea [Leading country], Indonesia, Malaysia, Philippines, Thailand, Vietnam
A variety of foods such as rice and egg were suggested as target materials. On the other hand, a composite target was suggested as target material representing the daily dietary intake. Implementation plan is supposed to be coordinated by future discussions.

Initial indication of participation : Bangladesh, China, Indonesia, Japan [Leading country], Malaysia, Thailand, Vietnam

This activity has a plan to monitor the spatial and temporal variation of pollutants in marine sediments including estuarine sediments and on-shore samples.

Participants of the NAA workshop

Research Reactor Technology (RRT) Workshop was held for 5 days on October 19 - 23, 2008 and participated by 13 representatives from 8 FNCA member countries, namely Bangladesh, China, Indonesia, Japan, Korea, Malaysia, Thailand and Vietnam.
New theme of Research Reactor Technology (RRT) project is “Sharing Safety Analysis Techniques for Safety Operation of Research Reactors” and the title is “Safety Analyses of RIA (Reactivity Initiated Accident) and LOFA (Loss of Flow Accident) for Research Reactors”.
The objective of the project is to improve and equalize the level of safety analysis techniques among participating countries to assure the safe and stable operation of research reactors for the promotion of effective utilization.

The following codes are selected as common codes for safety analyses.

  (1) COOLOD-N2: Steady state thermal hydraulic code
  (2) EUREKA2/RR: Nuclear & thermal hydraulic coupling code for transient change

In the workshop, participants exchanged several information about the current status of safety analysis of the research reactor in each country. The outline of Steady state thermal hydraulic code COOLOD-N2 was explained and the support on installing this code was provided. They discussed the implementation plan over the next 3 years and agreed.

FNCA open seminar was held during the workshops on October 20, 2008. The workshop participants from Japan, Vietnam and Australia gave the special lectures as follows;

“Nuclear Energy Policy and Plan in FNCA Countries and Japan” Dr. Sueo Machi (Japan)
“Nuclear Energy Policy and Plan of Viet Nam for Sustainable Development” Mr. Hoang Anh Tuan (Vietnam)
“OPAL Research Reactor and applications” Dr. J. W. Bennett (Australia)
“Perspective of Research Reactor Application in JAEA” Dr. Kiyonobu Yamashita (Japan)
“Application of NAA for geo-Environmental Assessment and Mineral Resources Exploration” Prof. Tsuyoshi Tanaka (Japan)

There were 41 participations from local research organizations, an educational organization, an authorities concerned and so on.

The participants of both workshops visited Dalat Nuclear Research Institute (NRI) and observed the reactor “TRIGA MARK-II”.

Summary Report of
FNCA 2008 Workshop on
Neutron Activation Analysis (NAA) Group

Following the welcome by the chairman of the organizing committee, Dr Nguyen Nhi Dien, Director, Nuclear Research Institute, Vietnam Atomic Energy Commission, the session began with the introduction of participants, their experience and involvement in FNCA activities.

Prof. Mitsuru Ebihara, NAA Project Leader, presented opening remarks on the activities to be carried out during the workshop, including:

1. Country reports on NAA activities and applications of research reactors
2. Development of an implementation plan for the new phase of NAA sub-projects in the areas of:
   1. Geochemical mapping and mineral exploration
   2. Monitoring food contaminants
   3. Monitoring environmental contamination
3. For each of the sub-projects there was to be a lead speech, followed by presentations on country activities and plans and discussion of objectives, goals and implementation plans.

I. Country Reports

The following country reports were presented by each national representative, in country alphabetical order:

Australia : Dr. John W. Bennett
The 20 MW open-pool light-water research reactor, OPAL, is operated by the Australian Nuclear Science and Technology Organisation (ANSTO). It is used for the production of medical and industrial radioisotopes, the irradiation of silicon ingots, neutron scattering science using cold and thermal beam lines, the irradiation of materials for research, and NAA and DNAA. Separate NAA rigs are available for short and long irradiations, at fluxes from 3×10¹² to 1×10¹⁴ n cm^-2 s^-1. The k₀-DSM software will be used to carry out NAA calculations in most cases. NAA projects are being scheduled in the research fields of environment, geoscience, mineral exploration, archaeology and materials science.

Bangladesh : Dr. Syed Mohammod Hossain
The Bangladesh Atomic Energy Commission (BAEC) has operated the country's only research reactor, a 3 MW TRIGA Mark-II, for the last 22 years. Tasks have included isotope production, material research using neutron scattering, materials characterization by neutron radiography, and the use of NAA for the qualitative and quantitative assessment of elements in variety of sample matrices. Examples of R&D work include: 1) the recent determination of neutron capture cross-sections at a thermal energy of 0.0536 eV using a triple axis spectrometer (TAS) and NAA; and 2) the analysis of six marine sediment samples collected from the Bay of Bengal using NAA and a comparison of those results with analyses carried out using AAS. A large component of the service work of the NAA lab is to carry out arsenic analyses for projects concerned with the assessment and mitigation of arsenocoisis in people exposed to contaminated groundwater.

China: Mr Huang Donghui
In China there are several research reactors available for neutron activation analysis including a 3.5 MW swimming pool reactor (SPR) and several 27 kW miniature neutron source reactors (MNSR). The 60 MW China Advanced Research Reactor (CARR) is scheduled to reach criticality in 2009. In CARR, new NAA facilities will be constructed over the next 5 years and will include DNAA and PGNAA (thermal and cold). There are about 100 people in China engaged in NAA. Current work in the group led by Prof. Bangfa Ni includes: SRM/RM certification and further research; studies of NAA methodology for the k₀ and relative method; using nuclear analytical methods (primarily NAA) to improve air quality in the RCA region; and conventional sample analysis service.

Indonesia: Mr. Sutisna
The NAA activities and research reactor utilization of all three of BATAN's reactors were presented. The reactors have been used in a wide range of fields, such as radioisotope production, materials science, nuclear instrumentation, as well as NAA. All NAA laboratories have been installed with equipment and software to enable both k₀ and relative NAA to be carried out. The NAA laboratories located at Bandung and Yogyakarta have been accredited to ISO/IEC 17025:2005 by the National Accreditation Body, whilst the NAA laboratory at Serpong is in the process of achieving accreditation. A total of 7 staff are engaged in NAA. The main applications of NAA are in the fields of health (whole blood and human specimen samples), environment (marine contaminant analysis and food safety analysis), industry (cosmetic and industrial products) and material characterization (microspheres and nanotechnology). The preliminary results of food contaminant analyses and essential elements analyses were presented in detail.

Japan: Prof. Mitsuru Ebihara
The current activities and ongoing plans of NAA in Japan were presented in the context of the availability of research reactors. There are three reactors that could potentially be used for NAA but two of them are now temporarily suspended. These reactors are expected to be reopened in 2009. Plans have been submitted for the construction of a new PGNAA system with multiple Ge detectors and using a proton accelerator as a source of neutrons. In addition, activities of the Japan Association of Activation Analysis (JA³), an association devoted to activation analysis, were presented.

Korea: Mr Jong-Hwa Moon
NAA activities and applications of the HANARO research reactor in Korea were presented. HANARO, which is the only research reactor in Korea, has now operated successfully for more than 2,000 days since it was opened in 1995. Three facilities for INAA, PGNAA and DNAA have been implemented and applied to the analysis of a variety of samples. In this presentation, environmental studies using INAA applied to sewage sludge, bottom ash from a coal power plant and stream sediment samples were described.

Malaysia: Mr Md Suhaimi Bin Elias
The 1 MW TRIGA MK II reactor has been in operation since 1982. It is used for small angle neutron scattering (SANS), neutron radiography and NAA. NAA has been used to carry out elemental analyses of environmental, geological and food samples. Recently, NAA has been used to analyse marine sediments from nine sampling locations along the Sabah coast. Twenty-nine elements were analysed including toxic elements such As, Cr, Sb, and Zn. Further studies will need to be conducted to identify the source of the elemental pollution found at some sampling sites. The data obtained from this study will provide crucial information on the current status of marine environmental pollution in Malaysia, particularly along the Sabah coast.

Philippines: Ms Preciosa Corazon B. Pabroa
The Philippine Nuclear Research Institute involvement in the FNCA sub-group project on NAA is primarily focused on the capability of the institute to analyze environmental samples using EDXRF to produce data for comparison with NAA results measured elsewhere. This approach provides the opportunity to validate XRF data with an independent analytical technique. Research is being carried out on air pollution, mineral exploration and elemental characterization of water in support of isotope hydrology research. A PGNAA system is currently being set up. Collaborative or support linkages have been established with the Environmental Management Bureau, Palawan local government, Makati Environmental Protection Council, ANSTO, University of the Philippines and the Dept. of Science and Technology.

Thailand: Dr. Sirinart Laoharojanaphand
The organization chart of the newly established Thailand Institute of Nuclear Technology (TINT) that separated very recently from the Office of Atoms for Peace was presented. One of the roles carried out by TINT is the operation of the Thai Research Reactor TRR1/M1, a 1.2 MW TRIGA Mark III swimming pool reactor. The reactor is used for NAA, isotope production, neutron scattering, gemstone enhancement and mutation breeding. A variety of NAA techniques are available, including INAA, ENAA, PGNAA, and PNAA/RNAA. A number of new techniques are being developed. NAA has been applied in various fields including environment, food and health, minerals and mining, industry, agriculture and archaeology.

Vietnam: Mr. Vu Dong Cao
The 500 kW Dalat Research Reactor, modified from a TRIGA Mark II reactor, is used for radioisotope production, NAA, PGNAA, basic and applied research and training. About 1,000 samples are analysed by NAA per year, in the fields of geology, oil field study, environmental science, archaeology, etc. The laboratory is in the process of moving from the use of the k₀-DALAT software to k₀-IAEA. Initial results of an NAA study of clay samples and brick specimens collected from the prehistoric site of Cattien and other places were presented. Multivariate analysis methods, principal components analysis (PCA) and cluster analysis (CA), were used for provenance determination. The work is being carried out at the INAA laboratory of the Nuclear Research Institute (NRI), Dalat, through a ministry project regarding provenance research in archaeology.

II. Plans for the New Phase

For each of the suggested sub-projects a lead presentation was made in which an overview was provided and possible project goals were suggested. Presentations were then made by each of the countries that had previously expressed an interest in being involved in each sub-project.

1. Geochemical mapping and mineral exploration

Lead Presentation - Dr John W. Bennett (Australia)
A sub-project in geochemical mapping could have benefits for: mineral exploration; environmental monitoring; the health of crops, animals and humans; and decisions about land use. The sub-project has the potential to be recognised by national stakeholders as being high profile, relevant to national priorities, able to deliver significant benefits and to take advantage of the strengths of NAA. The scope of the sub-project is broad enough that individual countries can select components that match the technical resources available. The sub-project could deliver quantifiable outcomes for socio-economic benefit, under the theme of ‘Good science making a difference’. It would be important to undertake laboratory inter-comparisons and benchmarking of NAA between participating countries using reference materials. As a first step, each participating country is requested to seek input from the appropriate national authorities and research community to determine the nature and level of possible involvement of NAA.

Dr Syed Mohammod Hossain (Bangladesh)
A survey has recently been conducted along the 20 km coast of Cox's Bazar (from Laboni Beach to Inani Beach) to investigate the geochemical composition of heavy mineral deposits. The work was carried out in collaboration with the Beach Sand Minerals Exploitation Center (BSMEC). Sand deposits were collected from 21 locations at an interval of 1 km and at 3 different depths. Heavy minerals like ilmenite (FeO.TiO₂), magnetite (FeO.Fe₂O₃), garnet [(Fe, A, Ca, Mg, Mn) (SiO₄)], rutile (TiO₂), etc., separated by BSMEC, have also been collected for the determination of impurities in them. The analysis is in progress.

Mr Huang Donghui (China)
A project was described that aims to develop a new class of certified reference materials (CRM). The CRM's are required for quality control of solid sampling microanalysis. The certification process employs several available nuclear analytical techniques, including NAA. Such CRM's may contribute to the geochemical mapping and mineral exploration sub-project.

Prof. Tsuyoshi Tanaka (Japan)
Geochemical maps represent an efficient means of providing basic information for geo-environmental assessment and resource exploration. INAA is recognised as the best method for analysing multiple elements in multiple samples collected from a wide area. The Department of Earth and Environmental Science at Nagoya University has developed a convenient procedure that has been applied to the analysis of more than 2,000 stream sediment samples. Trace elements in insoluble minerals such as zircon can be determined with better reliability by INAA than by ICP-MS. A geochemical map for La, Ce, Sm, Eu, Yb, Lu, Sc, Cs, Au, As, Sb, Th, U showed interesting features in the Nagoya-Toyota-Seto region.

Mr Md Suhaimi Bin Elias (Malaysia)
National priorities in Malaysia include the assessment of marine environmental pollution, characterisation of airborne particles, determination of essential and toxic elements in the Malaysian diet and geochemical pollutants in anoxic sediment of marine and fresh water bodies. Land-based geochemical mapping is not currently of high priority.

2. Monitoring of food contaminants

Lead presentation - Mr Jong-Hwa Moon (Korea)
NAA may play an important role in quantifying both essential (e.g. I, Ca, Fe, Se, Zn) and toxic elements in food (e.g. As, Pb, Cd, Cr). Possible applications might be focused on main dishes, dietary supplements, seafood, meat, etc. There would need to be a consensus between participating countries on the focus and goals of the project. It was pointed out that limits of detection of the NAA technique would need to be considered very carefully. A detailed study of the elemental composition of the component parts of ginseng was presented as an example of a possible approach.

Dr Syed Mohammod Hossain (Bangaladesh)
Fifteen samples of fruit and vegetables were collected from five locations in the Upazila of Feni district and were analyzed for arsenic contamination. The results revealed that the arsenic levels were below the detection limit (0.6 mg/kg dry weight) in all except three arum samples. Thirteen fruits and vegetables grown around the reactor were collected for elemental analysis with the aim of creating a baseline dataset. That analysis is in progress.

Mr Sutisna (Indonesia)
The results of a project carried out to determine the elemental analysis of a range of staple foods obtained from markets around Banten and Jakarta were presented. Samples of cacao, cereals, beans, vegetables and rice have been analysed to determine both essential elements (e.g. Na, K, Zn, Fe and Se) and contaminant elements (e.g. Cr, As, Sr, Sc and Mn). Details of the sample preparation, irradiation conditions and data analysis were provided.

Mr Md Suhaimi Bin Elias (Malaysia)
A project is currently being undertaken to determine essential and toxic elements in food of an average Malaysian diet, considering various Malaysian cuisines and different types of diet. Recommendations are being formulated with respect to sampling, including sampling area, type of food and food outlets (restaurants and food stalls). Constraints include budget limitations, reactor availability and the need to manage customer perceptions of priorities.

Dr Sirinart Laoharojanaphand (Thailand)
A project to monitor contaminants in Thai food items is being undertaken. The project will involve the NAA analysis of nutrients and toxic minerals. The project is being undertaken in close collaboration with the Institute of Nutrition, Mahidol University, Salaya, Nakhonpathom, Thailand. Selected items are being sampled from four food groups: cereals and products; starchy roots, tubers and products; legumes, nuts, seeds and products; and fin-fish, shellfish, other aquatic animals and products. Sampling and sample preparation will be carried out by the Institute of Nutrition according to a specific protocol. The results will be used to update the Thailand Food Composition Table.

Mr Giang Nguyen (Vietnam)
A market basket study in 2009 will involve the collection of 100 foodstuffs from city and countryside locations in Lamdong, Phuyen, Nhatrang and Binhdinh provinces. The concentration of trace elements such as As, Cd, Cu, Hg, Sb, Se, Pb and Zn will be analyzed by INAA, RNAA and AAS. The daily intake of the elements for adults in the different provinces will be estimated.

3. Monitoring of environmental contamination

Lead presentation - Prof. Motoyuki Matsuo (Japan)
Target materials may be solid environmental samples in the form of airborne particulates (already dealt with in Phases 1 & 2), sediments (river, lake and marine), soils etc. A prime candidate may be marine sediment, focusing on the coastal environment. Questions may be addressed that are related to major and trace elements, toxic or harmful elements, natural or anthropogenic origin, etc. There may be significant interest in extending the scope of the sub-project to include the determination of environmental change by studying core samples of sediments. It will be important for there to be agreement between participants on common samples and sample treatment, common technical methods and common analytical methods (including software). The benefits of the project would be a quantification of marine environmental pollution in Asian countries and of environmental change in coastal areas over time. Results should be published in high quality journals. Two case studies were presented.

Dr Syed Mohammod Hossain (Bangladesh)
Three case studies were presented. The first concerned groundwater contamination with arsenic and considered the geochemical and hydrological implications. The second compared the composition of Bay of Bengal sediments with agricultural soils of Bangladesh, focusing on the elements U, Th, As, Sb and Cr. The third presented a project that has just begun to monitor environmental contaminants due to ship-breaking. Pollutants may include Cd, As, Zn, Cr, asbestos and persistent organic pollutants, all of which may pose a threat both to workers and to the coastal inter-tidal zone.

Mr Sutisna (Indonesia)
A number of projects were described that would have matched the proposed theme but which had failed to be approved for budgetary reasons. This included the project on The Analysis of Pollution and Pollutant Sources at Industrial Region, proposed for 2008. Meanwhile the project on The Use of NAA to Determine The Environmental Status of Musi River at South Sumatra had failed to obtained funding from the 2008 Incentive Program of the State Ministry of Research and Technology. A new project on Environmental Pollution in the Industrial Region of Banten, to commence in 2009, has been proposed but is still awaiting approval. Dr Sueio Machi, FNCA Coordinator of Japan, offered to approach relevant decision-makers in Indonesia to stress the potential importance of the proposed projects.

Mr Md Suhaimi Bin Elias (Malaysia)
Two projects were described that fit within the sub-project. The first was in the assessment of marine environmental pollution, to quantify toxic and trace elements in marine sediments and to identify the sources of any contaminants. Sampling locations were identified in coastal areas of Sabah, Sarawak and the Malaysian peninsular. Three universities and three government agencies were nominated as collaborators. The second project described was a continuation of the program to characterise airborne particulates for the assessment of air quality.

Ms Preciosa Corazon Pabroa (Philippines)
There is an on-going study on the evaluation of the air quality in the area of a coal-fired power plant (Calaca, Batangas) using the lichen Pyxine cocoes as a biomonitor. Available APM and soil samples in the area will also be analyzed by EDXRF or INAA and/or PGNAA, depending on availability of the techniques. Another possible area of study is Los Banos, Laguna (located in Mt. Makiling) which is noted for its many hot springs. Relatively high sulfur levels have been measured in the area. The same research protocol would be followed as used at the Calaca sampling site.

Dr Sirinart Laoharojanaphand (Thailand)
A project is being undertaken to monitor marine environmental contamination in the inner Gulf of Thailand, using NAA and other relevant methods. Sediments and biological samples will be included and seasonal variations will be monitored. Sampling will be assisted through collaboration with the Department of Aquatic Science, Faculty of Science, Burapa University, Chonburi, Thailand. TINT will be responsible for the analysis of the samples. Information will be made available through Burapa University to the provincial environmental authorities.

Mr Giang Nguyen (Vietnam)
Ninh Thuan Province is being considered as a possible site for the construction of the first nuclear power plant in Vietnam. A primary data set of the present levels of elements in marine environmental samples is being compiled to assess present base-line conditions. The data set will be necessary to quantify changes in the marine environmental pollution load in the future. Samples will be collected from the coastal area of the Ninhphuoc and Ninhhai Districts in the Ninh Thuan Province. Sediment, seawater and biota will be sampled. More than 20 elements in the marine environmental samples will be determined by k₀ and relative NAA techniques.

4. Discussion of objectives, goals and implementation

After the presentations each suggested sub-project was discussed in turn. These discussions considered objectives, goals, potential for cooperation, work-sharing and road-mapping. In each case there was a focus on potential end-users.

a) Geochemical mapping and mineral exploration
In discussion it was made clear that this sub-project is multi-disciplinary by its nature and requires strong linkages with stakeholders, collaborators and end-users. Dr Machi reminded the forum that mineral exploration is an urgent need for the future of mankind. Three actions were agreed:

Countries would review their willingness to be involved in the sub-project after the first step of consultation.

b) Monitoring of food contaminants
Matters including the likely participation of individual countries, the selection of target samples and the development of action plans were discussed. In summary:

Firm conclusions were not reached and it was agreed that further discussion was needed in order to develop concrete set of goals and action plans. It was agreed that Mr Moon would initiate and coordinate this discussion of the food project by participating countries, using email.

c) Monitoring of environmental contamination
A common theme of ‘marine sediments’ emerged from the presentations of likely participants and in subsequent discussion. Some countries are focusing on the spatial variation of toxic elements in bays or around coastlines whereas others prefer to determine variations in the concentration of elements over time from the analysis of core samples. Offers were made by Dr Matsuo and Dr Hossain to share the technical details of sampling procedures. It was agreed that the sub-project would concentrate on marine sediments collected on the continental shelf but could also include estuarine sediments and on-shore samples. The importance of agreeing on sampling and analysis protocols to be used by all participating countries was stressed.

III. Summary and Conclusions

Three sub-projects were selected for the third phase of the FNCA NAA Project:

3.1 Geochemical mapping and mineral exploration
3.2 Monitoring of food contaminants
3.3 Monitoring of the spatial and temporal variation of pollutants in marine sediments

Table 1 summarises the sub-projects with regards to target materials and participants.

The workshop was formally closed by Professor Ebihara who thanked all participants for their valuable contributions and the very positive outcomes that were achieved.

  Table 1. Summary of FNCA NAA Project - Phase 3

Summary Report of
FNCA 2008 Workshop on
Research Reactor Technology (RRT) Group

1. Introduction

The last project with following theme was ended in March 2008 successfully.

“To share neutronics calculation techniques for core management on research reactors among the participating countries in order to assure safe and stable operation for effective utilization.”

New theme “Sharing Safety Analysis Techniques for Safety Operation of Research Reactors” for RRT- project was agreed in the 9^th FNCA Coordinator Meeting, Tokyo, Japan in 10. March, 2008.
The title is “Safety Analyses of RIA (Reactivity Initiated Accident) and LOFA (Loss of Flow Accident) for Research Reactors”.
The objective of the project is to improve and equalize the level of safety analysis techniques among participating countries to assure the safe and stable operation of research reactors for the promotion of effective utilization.

The following codes are selected as common codes for safety analyses.

2. Subjects

The subject of the 1^st workshop is to exchange the information on current status of safety analyses of each country, to demonstrate how to install and execute it and explanation of sample problem.

3. Opening

After the introduction of participating member, Japanese project leader Dr. Yamashita has informed that the new theme for the RRT-project is agreed in the 9^th FNCA Coordinator Meeting. He has explained the title and objectives as well as the 3 year schedule in Attachment A.
He also proposed subjects and schedule of the first workshop in Table 1. All participants agreed with his proposal.

Table 1  Subjects in the first work shop

During the opening, Dr. Yamashita presented specification of research reactors involved in this activity. It can be seen in Attachment B.

4. Participants

The workshop was attended by participants from Bangladesh, China, Indonesia, Japan, Korea, Malaysia, Thailand and Vietnam. The list of participants is attached in Attachment C.

5. Country Reports

(1) Bangladesh
“Current Status on Safety Analyses of 3 MW TRIGA MARK II Research Reactor of BAEC, Bangladesh” by Dr. Mafizur Rahman

The 3 MW TRIGA MARK II Research Reactor was commissioned in late 1986 at Atomic Energy Research Establishment, Savar, Dhaka, Bangladesh. The core consists of 100 fuel elements arranged in hexagonal array in a graphite reflector housing of 19.05 cm thick with an inside diameter of 54.9 cm. In understanding this core, neutronics analysis has been performed earlier using the codes WIMS-CITATION and repeated the same using computer codes SRAC and MVP which were provided by JAEA as common codes under the FNCA project on RRT. The codes NCTRIGA and PARET were used to analyze some important thermal hydraulic and transient analyses of the research reactor respectively. The safety calculation will be done in future with the codes COOLOD-N2 and EUREKA2/RR, supplied by JAEA as common codes under FNCA project on RRT in 2008. Under FNCA project, Bangladesh expects to improve the capability on thermal hydraulics and transient analysis of the TRIGA MARK II research reactor through sharing knowledge and experience in safety analysis with other participating countries. Bangladesh also desires to develop manpower in this field.

(2) China
“Current Status on Safety Analyses of China Advanced Research Reactor (CARR)”
by Dr. SHEN Feng

China Advanced Research Reactor (CARR), which will achieve the first criticality in June, 2009, is of tank-in-pool type, cooled and moderated by light water and reflected by heavy water. The rated nuclear power is 60 MW. The maximum undisturbed thermal neutron flux is 8×10¹⁴ n·cm^-2s^-1 in heavy water reflector.
Safety analyses of CARR, consisted of neutronics analyses, thermal hydraulics analyses and transient analyses, are abided by the codes and guides regulated by China Nuclear Safety Bureau. Since the safety analyses of CARR had been finished about two years ago, the common software SRAC and MVP, provided by JAEA as the common code under the FNCA project on RRT, couldn't satisfy the schedule of CARR project. The neutronics analyses are conducted by several codes, such as WIMSD4, CITATION, ORIGEN, MCNP and so on. The neutronics analyses results like power distribution and kinetic parameters were used as input data for thermal hydraulics analyses and transient analyses. The code CARRCO was used to calculate the parameters such as temperature, pressure and mass flow rate for fuel assemblies. The code of RELAP5/SCDAPSIM/MOD3.2 is used as transient analyses. The verification and validation of RELAP5 are proved by the good agreements between the results from RELAP5 and from new developed transient code for specific incident, and between the results from RELAP5 and the experiment results from the test loop. The analytical results could be used to modify the design and verify the safety characteristics for CARR. The share of COOLOD-N2 code and EUREKA2/RR code is welcomed and these two codes could be used as complementary safety analysis and analyses the safety characteristics for CARR.

(3) Korea
“Safety Analysis Process for the HANARO”
by Dr. Jonghark Park, Cheol PARK, Heonil KIM, Heetaek CHAE

The HANARO (Highly Advanced Neutron Application Reactor) is an upward flowing light water cooled, heavy water moderated open-tank-in-pool type research reactor. It was designed to meet the growing need for a high intensity neutron source in the area of national nuclear research and development such as various neutron beam applications, fuel and material testing, isotope production, neutron activation analysis and neutron radiography etc.
To meet the safety objective for protecting individuals, public and environment against radiological hazards, HANARO has been designed, constructed and operated to achieve the fundamental safety requirements that the safe shutdown and adequate cooling of the reactor is not jeopardized and the release of fission product is well prevented. The safety analyses were done to ensure that radiation exposure and release of radioactive material are below allowable limit by confirming that the design criteria of components.
To conduct the T/H analysis and the safety analysis for HANARO, the MATRA-h and the RELAP5 were adopted. The MATRA-h code was used for the steady state T/H calculation. And the RELAP5 code was adopted for the transient state analysis. Through the some safety analyses of HANARO, it was revealed that the reactor system and components were designed to be satisfied their specified functions against any postulated accident.
Under the FNCA activity, Korea expects the sharing of the knowledge and know-how for the T/H analysis and the safety analysis of a advanced research reactor using a plate type fuel.

(4) Japan
“Current Status of Safety Analyses Method of Japan Research Reactor-4 (JRR - 4)”
by Mr. Nobuhiko Hirane

Japan Research Reactor 4 (JRR-4) is a light water moderated and cooled, swimming pool type research reactor. The maximum thermal power is 3.5MW. JRR-4 is utilized for irradiation experiments, silicon irradiations, education for reactor engineers and medical irradiations. The core consists of 20 fuel elements, 5 control rods (4 shim rods and 1 regulating rod), and 36 reflectors. The fuel elements of JRR-4 are plate type fuel made by low enriched silicide (U3Si2-Al) fuel with aluminum cladding. Control rods are made by boron dispersed stainless steal. The reflectors are made by carbon graphite with aluminum casing and aluminum block.
In Japanese safety guide for research reactor, safety limits is provided, for example DNBR shall be greater than 1.5, the maximum fuel meat temperature shall not be over 400℃ and pressure of primary cooling system shall not be over 1.1 times of design pressure. And research reactors must satisfy these safety limits at every operational condition.
For safety analyses and thermal hydraulic design of JRR-4, Steady-State-Thermal-Hydraulics calculation code "COOLOD" (previous version of COOLOD-N2) and Reactivity-Accident analysis code "EUREKA2" (previous version of EUREKA2/RR) have been applied. In cases of normal operation (forced convection mode and natural convection mode) and flow channel blockage conditions, COOLOD code has been used for analyses on steady state thermal hydraulics. On the other hand, in case of operational transient and accidental condition such as reactivity insertion, pump coast down, loss of electric power supply, LOFA and so on, EUREKA2 code has been used for analyses on transitional condition. Consequently, results of safety analyses by COOLOD code and EUREKA2 code satisfied every safety limits, and safety of JRR-4 was proved.

(5) Malaysia
“Current Status on Safety Analyses at 1MW Reactor TRIGA PUSPATI (RTP)”
by Mr. Mohd Fairus Abdul Farid

RTP is a light-water moderated and pooled type research reactor with 1 MW capability. The RTP is equipped with various irradiation facilities and experimental facilities for beam experiments including NAA, SANS and NR. Besides, RTP also has been used as an education tool to the universities. It uses standard TRIGA fuel developed by General Atomic in which the zirconium hydride moderator is homogenously combined with enriched uranium. The RTP core has a cylindrical configuration with an annular graphite reflector.
The reactor has 111 stainless steel-clad fuel elements with 20% enrichment for 8.5wt%, 12wt% and 20wt% uranium concentration type, 9 graphite elements, 4 control rods, 2 irradiation channels and a neutron source. A graphite reflector enclosed in an aluminium casing surrounds the reactor core.
The safety analysis calculation in Malaysian Nuclear Agency currently is embarking of using RELAP5 computer code for steady state and transient calculation of RTP. It uses a one-dimensional, two-fluid model, consisting of steam and water. For the research reactor like RTP, this code is rather complicated.
As member state of FNCA, Malaysian Nuclear Agency has shown its commitment on the FNCA projects. As example, Malaysian Nuclear Agency had succeeded to use SRAC and MVP for RTP neutronics calculation by participating in the last project. With the new project “Safety Analyses of RIA (Reactivity Initiated Accident) and LOFA (Loss of Flow Accident) for Research Reactors”, Malaysian Nuclear Agency hopes to use the thermal hydraulics code COOLOD-N2 and transient analyses code EUREKA2/RR for RTP safety analyses.

(6) Indonesia
“Current Status of Thermal Hydraulics Calculation Method of RSG-GAS Reactor”
by Mr. Muhammad Darwis ISNAINI

The Multipurpose Reactor of GA. Siwabessy (RSG-GAS), formerly called MPR-30, is a pool type reactor that uses light water as coolant and moderator. RAS-GAS is a material testing reactor (MTR) type research reactor, that uses low enriched uranium (19.75 w/o) fuel elements with 2.96 gU/cm³ meat density. The reactor has 30 MW nominal thermal power. Thermal neutron flux at irradiation facilities can reach 2 x 10¹⁴ n/cm²/s. Originally, the oxide fuel (U₃O₈-Al), was used in the core, but presently, the silicide fuel (U₃Si₂-Al) has been used. Under the FNCA project, the fuel management calculation had been carried out using SRAC code. The core thermal-hydraulics characteristics and safety margin for the first, second, third and typical working core (40 FE and 8 CE) have been determined using several codes like HEATHYD, COOLOD-N, PLTEMP and PARET. However, the calculated results showed that several parameters of the typical working core were not well satisfied. The item that not satisfied was the temperature rise across the core and the maximum central fuel temperature at rated and over power. The investigation of the core thermal-hydraulics characteristics and safety margin of the typical working core of RSG-GAS for the SAR technical data that have been determined by Interatom, were carried out using the COOLOD-N code. The calculation result for oxide fuel, nominal power of 30 MW and over power of 34.2 MW using COOLOD-N AXP (main frame computer) and PC version, showed very good agreement on the coolant, plate and meat temperature distribution, the heat flux and the heat generation distribution. From these results, it can be concluded that COOLOD-N code can be used in determining the core thermal-hydraulics characteristics and safety margin of RSG-GAS. In the future, for updating the Safety Analysis Report of RSG-GAS for steady state and transient condition, COOLOD-N2 and EUREKA2/RR code will be used.

(7) Thailand
“Current Status on Safety Analyses of Thai Research Reactor (TRR-1/M1)”
by Mr. Chanatip Tippayakul

Safety analyses of Thai Research Reactor-1/Modification 1 consist of neutronics analysis, thermal hydraulics analysis and transient analysis. The current TRR-1/M1 core loading is core no.17 which was loaded in August 2008. In determining and analyzing this core loading, neutronics analysis using SRAC and MVP computer codes, which were provided by JAEA in the previous FNCA project on RRT, were employed to determine the maximum peaking factor. COOLOD-N2 computer code, which was provided by JAEA in the bilateral agreement with Thailand, was used to analyze the temperature distribution including maximum fuel temperature as a function of reactor power. The use of SRAC, MVP and COOLOD-N2 proves to be a good practice to perform safety analyses of the new core loading. Moreover, in a previous work, Thailand had participated in the bilateral project with Japan on “research reactor technology involving using COOLOD-N2 and EUREKA2/RR for thermal hydraulics and transient analyses of TRR-1/M1”. The COOLOD-N2 model for steady-state (natural convection) condition and the EUREKA2/RR model for transient condition were created and validated with the experiments and they were found to be sufficiently accurate.
In the FNCA project, Thailand hopes to advance the COOLOD-N2 and EUREKA2/RR modeling through the cooperation. Although Thailand has some experience in using these codes to model TRR-1/M1, the models need more improvements to be in better agreement with the measurements. For COOLOD-N2, the current model is still overestimating the measurement values. Additional studies on the COOLOD-N2 code and adjustments on the -DN2 model shall provide opportunities to investigate the overestimation. Moreover, the EUREKA2/RR modeling can be significantly improved in the FNCA project. Until now, Thailand has only performed reactivity insertion analysis but has not performed loss of flow and loss of coolant accidents which are new areas for transient analysis studies of TRR-1/M1. Thus, the EUREKA2/RR models on these topics are to be created in the FNCA project. Thailand believes that the improvement of the modeling can be done by sharing and exchanging the knowledge and expertise with other participating countries. As the ultimate outcome of the FNCA project, Thailand wants to increase the competency of the personnel in performing these analyses so that the technology can be transferred to the NPP reactor engineers for the future Thai NPP project.

(8) Vietnam
“Current Status on Safety Analyses of Dalat Nuclear Research Reactor”
by Mr. Luong Ba Vien

Dalat Nuclear Research Reactor (DNRR) is a light water moderated and cooled, pool-type reactor fueled with 36% enriched VVR-M2-type U-Al alloy and with 19.75% enriched VVR-M2-type UO₂-Al dispersion fuel. The reactor can be operated at a maximum power of 500 kW.
Safety analyses of DNRR consist of neutronics analysis, thermal hydraulics analysis and transient analysis. The current core of DNRR is a mixed fuel core using both HEU-VVR-M2 and LEU-VVR-M2 fuel assemblies which were loaded on 12 September 2007. In order to analyze the mixed fuel core loading, computer codes SRAC, MCNP, WIMS-ANL and REBUS were used for neutronics analysis. In analyzing the steady state thermal hydraulic and transient conditions, COOLOD-N2 and RELAP5/MOD3.2 were also used. The use of SRAC and COOLOD-N2 codes, which were provided by JAEA, have proven to be a good practice to perform safety analyses for the mixed fuel core loading and fuel reloading later on. Besides, the SRAC, MVP and COOLOD-N2 codes have been also used for safety analyses of a conceptual core of a new 20 MW multi-purpose research reactor for Vietnam. Through the participation in the new theme for RRT Project on “Sharing safety Analysis Techniques for Safety Operation of Research Reactors”, Vietnam hopes to improve the modeling of thermal hydraulics and transients of DNRR and the new research reactor by using COOLOD-N2 and EUREKA2/RR, and also to share the information and knowledge among participating countries. In addition, Vietnam also desires to increase the competence of personnel in the field of safety analysis for research reactors.

As a summary of country report, thermo-Hydraulic code used at present are attached as Attachment D and reactivity accident analysis code at present is attached as Attachment E.

6. Outline of COOLOD-N2 Code

COOLOD-N2 is a computer code for analysis of Steady-State Thermal Hydraulics and used for design of JRR-2, JRR-3, JRR-4 and JMTR in Japan. COOLOD-N2 can calculate fuel temperature, coolant temperature and pressure, ONB temperature, Departure from nuclear boiling ratio (DNBR) and so on under steady state condition. And can treat variable kind of fuel and coolant, condition of coolant flow. In COOLOD-N2 code, some models and correlation is adopted. And they are properly selected on the condition of calculations.
An experiment was carried out for verification of COOLOD (previous version of COOLOD-N2). The experiment is measurement of fuel temperature, using instrumented fuel (thermocouple implanted). The results of measurement agreed with result of calculation, so that the propriety of COOLOD had been confirmed by experiment.
There are some questions from participates, such as how to select heat transfer correlations, about results of experiment for fuel temperature measurement and so on. Mr. HIRANE answered these questions and obtained understandings of participants.

7. Demonstration of Installation and Execution of Sample Problems on COOLOD-N2

Mr. HIRANE explained and demonstrated the installation and execution of COOLOD-N2 with distributed CD. Thereafter, interpreted sample input data of COOLOD-N2.
After the demonstration, there are some questions about batch file and how to run the program from participants. Mr. HIRANE answered and helped them, and all problems were resolved.

8. Practical Training of COOLOD-N2

Participants practiced the installation and the calculation as well as the procedure of the demonstration. Afterward, the maximum temperature of fuel and minimum DNBR were chosen from calculation results, and these were compared with results of the example. It was confirmed that each calculation was correctly done. Thereafter, Mr. HIRANE explained outline of COOLOD-N2 input data.
There are some questions about the result of calculation and meaning of input data, and these questions were resolved by the discussion among participants.

9. Current Status of Using COOLOD-N2

Every country finished to submit the permit for using COOLOD-N2 and received CD of COOLOD-N2. Although some countries had not succeeded in installing COOLOD-N2 and executing sample program before workshop, every country has succeed during the workshop.
The current status of using COOLOD-N2 are shown in Attachment F.

10. Discussions and Summary

The current status of safety analyses has been presented from each country in detail during the workshop. Some countries have used safety analysis codes which were developed actually for power reactors and are not convenient for research reactors due to the sophisticated and complicated structure. They expected convenient safety analysis code for research reactor. Every country presented the current status of installation and execution of COOLOD-N2 distributed prior to the workshop from Japan. Some difficulties encountered in installation and execution are solved with cooperation of participating members during the workshop.
Participating members have agreed that all members support and help each other in solving problems. Especially, the cooperation among the countries having similar facilities is strongly expected.
Expectations for the project from each country are shown in Attachment G.
Japan has proposed the future project activities for 2009 and 2010. After the discussion, the future activities have been agreed as given in Table 2 and Table 3.

Table 2  Project Activity for 2009

Table 3  Project Activity for 2010

List of Participants
FNCA 2008 Workshop on
The Utilization of Research Reactors