1. NEUTRON ACTIVATION ANALYSIS

The 2003 FNCA workshop on the utilization of research reactors for the NAA group was held at Dalat, Vietnam on 12-16, January 2004, with participants from China, Indonesia, Japan, Korea, Malaysia, Philippines, Thailand and Vietnam. The workshop consisted of two meetings; one was allocated for ko method on 12th and another was for main discussion on the remaining days. The ko-related meeting was held at the Nuclear Research Institute and the main meeting was at the Sofitel hotel, Dalat. This report consists of three parts; a summary of the ko-session, a summary of country reports and a summary of “round-table” discussions.

1.1. SUMMARY OF THE Ko-SESSION
The first day of the workshop (12th January) was allocated for the ko-method. At the beginning of the session, all participants were welcomed by peoples of the Nuclear Research Institute. Following the short ceremony, ko-experiment was performed for several samples brought from Japan, which are three geological reference samples having well certified values. After the lunch break, we heard the current status of ko-method in each participating countries, as summarized in the following. Among them, there were two long presentations by Japanese and Korean participants, which are summarized separately below. Finally, calculated results by using ko-Dalat were live-shown mainly for short-lived nuclides and were compared with literature values. Generally, most of elements (Al, Ca, K, Mn, Na, Ti and V) were consistent with literature values, although one or two eelements (Mg/Dy) were found to be different from literature values.

1.3. summary of “round-table” discussions
At the “round-table” discussions, the following subjects were taken up;
          (1) The 2002 report
          (2) Progress in 2003
          (3) Plan for 2004
          (4) ko-method
          (5) New project(s) for the next term
Minutes are summarized individually for each of them.

(1) The 2002 report
At the last year’s workshop at BATAN, Indonesia, we agreed to prepare the manuscript of chemical compositions of PM samples collected in 2002 and discussed a possible timetable and a practical procedure. According to the agreement, data and accompanying information were sent to Japan by September 1, 2003 (2nd and postponed deadline) from five countries (Japan, Korea, Malaysia, Philippines and Thailand). Based on these data, the manuscript was prepared by Japanese representatives with many efforts and was distributed to other countries by email prior to the workshop. At the workshop at Dalat, it was discussed how to handle the draft at the next stage. After extensive discussion, it was agreed that (i) the manuscript would be submitted to an appropriate journal at the present form, that is, no additional data from other countries would not be incorporated so that any further delay could be avoided, (ii) any correction should be made as soon as possible and no later than January 30, 2004, (iii) data from Indonesia would be incorporated if its incorporation makes any additional delay, (iv) any correspondence should be addressed to the project leader (M. Ebihara) with cc to other Japanese participants, and (v) a final draft would be submitted in February, 2004.

(3) Plan for 2004
As a year of 2004 is the final year for the current term, we are to be continuously working on the presently standing (main) project, that is, collecting and analyzing airborne particulate matter by NAA. At the next workshop, it is required for all participants that data of PM samples collected during the term of 2002-2004 are summarized. Current status for the PM project is summarized below (as of January 16, 2004).

	(i)	Name of sub-project: QC/QA of INAA data among FNCA countries
	(ii)	A person in charge: Dr. Abdul Khalik Bin Wood (Malaysia)
	(iii)	Experimental procedure: A geological standard reference material (in powder) is used. Korea is responsible for preparing and distributing such a sample to participating countries. An aliquant of about 100mg is used for one specimen. In Philippine, XRF is to be conducted so that INAA data can be compared with XRF data. For XRF, 2 g sample is used. At least, six measurements are to be done. A detailed instruction will be prepared by Khalik and be distributed to our group. Data should be sent to Khalik one month prior the next workshop.

(5) New project(s) for the next term
Although one more year is allocated to the current project, we have started to discuss new project(s). Before starting the discussion on this matter, we confirmed that this FNCA/NAA workshop was profitable for all participating countries and, therefore, was hoped to be continued after the current term was terminated in 2004. Then, we have discussed new project(s) for the next term starting in 2005. Following a proposal by Vietnam at the 2002 coordinators’ meeting, marine samples were discussed for our next target from several viewpoints. With recognition of their importance for monitoring the marine environment, it was agreed that marine samples could be a main target for the next term. After free and lively discussion, it was unanimously agreed that marine biota could be an appropriate substance. The detailed guideline for the analysis of biological substances will be discussed at the next year’s workshop. Until then, each country is required to consider any aspect which could be incorporated in the guideline. For helping us in having an experience of analyzing marine biological samples, Japan will find an appropriate SRM of marine biota and send its aliquants to all group countries if available.

The 2003 FNCA workshop on the utilization of research reactors for the NAA group was held at Dalat, Vietnam on 12-16, January 2004, with participants from China, Indonesia, Japan, Korea, Malaysia, Philippines, Thailand and Vietnam. The workshop consisted of two meetings; one was allocated for ko method on 12th and another was for main discussion on the remaining days. The ko-related meeting was held at the Nuclear Research Institute and the main meeting was at the Sofitel hotel, Dalat. This reports consists of three parts; a summary of the ko-session, a summary of country reports and a summary of “round-table” discussions.

2.2 Country Reports
(1) China
“Status of Research Reactors in China” by Mr. Yuan Luzheng
Current status of research reactors in China was presented. Upgrading and renovations for the aging research reactors made them running safely. The progress of CARR project was described. Status of BNCT program in China was mentioned. Some proposals on research reactor technology for effective utilization were involved.

(2) Indonesia
“Improvement Plan on Utilization of the RSG-GAS Reactor” by Mr. Iman Kuntoro
As a multipurpose reactor, RSG-GAS provides facilities for utilization on material testing, radioisotope production, R&D using neutron irradiation as well as training. The reactor was brought into operation since 1987. Because of fact that national nuclear power program was delayed, so, R&D on material testing associated to nuclear power plant were not carried out. The reactor is operated mainly for serving radioisotopes production, neutron activation analysis, neutron beam experiments and general irradiation for research and development activity. Reactor description, achievements and improvement plan in conduct of operation and its utilization were discussed.

(3) Japan
“The Current Status of Research Reactors in JAERI” by Mr. Hisashi Sagawa
There are several research reactors including critical facilities in JAERI. Of these research reactors, JRR-3, JRR-4 and JMTR are utilized widely by a large number of researchers. The recent topics on utilization of JRR-3, JRR-4 and JMTR were presented, and the troubles which occurred in JRR-3 and JMTR recently were also presented.

(4) Korea
“Research Reactor Activities in Korea” by Mr. Byung Jin JUN
Two research reactors are in operation, another two are waiting for decontamination & decommissioning, and a feasibility study for a medical isotope production reactor is ongoing. Safe and effective management and the active utilization of the research reactors are important concerns of the Korean Government who funds the major part of the research reactor programs. The Government is promoting research for the non-power application of nuclear technology, for which research reactors have an important role as well as for nuclear power programs. Among the four research reactors, HANARO is the only facility providing a high neutron flux to various national demands. Its utilization and management records show remarkable improvement since its power operation in 1996, and ambitious national plans have been made for a further dissemination of its utilization.

(5) Malaysia
“The Present Status and Future Perpectives of PUSPATI TRIGA REACTOR” by Mr. Adnan Bokhari
The PUSPATI TRIGA Reactor, operated by the Malaysian Institute for Nuclear Technology Research (MINT) in Bangi has recently completed 21 years of successful operation. Since its commissioning in June 1982 to end of 2003, the 1MW pool-type reactor has accumulated more than 20,585 hours of operation, corresponding to cumulative thermal energy release of about 13,714 MW-hours. The reactors is equipped with five major types of experimental facilities, consisting of the central thimble, a rotary specimen rack, two pneumatic transfer systems, four beam ports and a thermalizing column. Presently, most of the operating hours are spent on irradiation of samples for the neutron activation analysis purpose. To enhance Malaysian research and development in reactor related technology, MINT has made a dedicated commitment to strengthen the utilizing and maintaining the reactor to its optimal usage.

(6) Thailand
“Progress Activity of Thai Research Reactor in 2002” by Mr. Sakda Charoen
Thai Research Reactor-1/Modification1 (TRR-1/M1) is a multipurpose research reactor with normal power of 2 MW. The reactor is a swimming pool type, cooled and moderate with light water, using the LEU-fuel. TRR-1/M1 has been operated and utilized for various applications such as neutron activation analysis, radioisotope production, gem irradiation, neutron radiography and research works. To expand and promote the utilization of research reactor, the new 10 MW Research Reactor will be established in the Ongkarak Nuclear Research Center (ONRC) project and the project will be finished in the near future.

(7) Vietnam
“Current Status of Operation and Utilization of the Dalat Research Reactor” by Dr. Nguyen Nhi DIEN
Outline of NRI and IVV-9, reactor management and the status of reactor utilization are presented.

“Application of Relap5/Mod3.2 Code for the Dalat Nuclear Research Reactor” by Mr. Le Vinh VINH
The safety principle and criteria of Dalat Research Reactor were introduced, and the results of thermal-hydraulics safety analysis using Relap5/Mod3.2 Code were also presented.

“Neutronics Analysis of Dalat Research Reactor” by Mr. Nguyen Kien CUONG
The calculation codes used for neutronics analysis in NRI were introduced, and the results of neutronics analysis using these codes were presented.

2.3 Proposal for new Project from each country
(1) The proposal from Japan
Prior to the proposal from participating countries, Japan delegate showed the aim of new Project. As fundamental technology on Research Reactor, the followings are considered.
- Development of irradiation field suitable to experimental purpose
- Technique to evaluate neutron field with accuracy
- Technique to supply stable neutrons
- Techniques to acquire irradiation data

(2) The proposal from China
Chinese delegate proposed the followings to enhance the experience exchange in extending field of utilization of research reactors.
- Service study on nuclear power plant development
- Techniques to improve the RI production
- Neutron transmutation doping of silicon
- Study on sea water de-salt technology
- Design or thoughts of new type reactor concept
- Experience in safety operation
- Renovation and upgrading measures
- Other utilization, such as cable exposure, gem irradiating, track-etched membrane, anti-bogus mark, etc.

(3) The proposal from Indonesia
Indonesian delegate proposed the followings.
- Development of irradiation facility
- Safety assessment of irradiation facilities and target
- Aging assessment technique

(4) The proposal from Korea
Korean delegate proposed the followings.
- Reactor physics
- Instrumentation and control
- Thermal-hydraulics analysis

(5) The proposal from Malaysia
Malaysian delegate proposed the following.
- Fuel management towards safe reactor operation

(6) The proposal from Thailand
Thai delegate proposed the following.
- Dynamic Neutron Radiography

(7) The proposal from Vietnam
Vietnamese delegate proposed the followings.
- Study on the upgrading and modernization of the reactor control and instrumentation systems
- Reactor core management including core analyses and measuring techniques

As the result of discussion, participating countries agreed that above “b&c” would be included in the Country Report as an information exchange. Considering above “a”, the followings were agreed by participating countries.

The title of the new project is “Research Reactor Technology (RRT) for Effective Utilization”.
The topic of the project is “Innovation of Research Reactors as Neutron Sources”.

The followings were determined as activities of “Innovation of Research Reactors as Neutron Sources” to improve basic technologies of research reactors.
- Reactor Physics (Neutronics)
- Thermal Hydraulics analysis
- I&C modification

2.5 Next year plan
In the 2004 Workshop, each country shall report on item “a” and items “b&c” separately, and concrete plan including activity item, schedule, details of activities in each year and so on will be discussed and determined based on the country reports.

3. Round Table Discussion

3.1 Workshop Summary
Under the chair of Dr. Nguyen Nhi Dien, PL of Vietnam, and Mr. T. Kosugi, acting PL of Japan, summary of the workshop of Neutron Activation Analysis and Research Reactors were reported by Professor M. EBIHARA and Mr. H. SAGAWA respectively. All participants of the workshop agreed the summary reports.

3.2 Additional remark at the Round Table Discussion
It was agreed to propose to 5th FNCA Coordinators Meeting that Thailand be the hosting country for the 2004 workshop by agreement of all participants for FNCA 2003 Workshop on Utilization of Research Reactors held in Vietnam.

SUMMARY REPORT OF THE 2003 FNCA WORKSHOP
ON THE UTILIZATION OF RESEARCH REACTORS
Sub-workshop on Tc-99m Generator Production
Expert Meeting of Neutron Scattering Experiment
January 12 –16, 2004
Jakarta/Serpong, INDONESIA

This document presents a summary on the implementation of the 2003 FNCA Workshop on the Utilization of Research Reactors held in Jakarta/Serpong from January 12 to 16, 2004. The workshop discussed two different fields of activities as technetium generator technology (TCG) in the sub-workshop and neutron scattering (NS) experiment in the expert meeting. It was attended by scientists and technical specialists from China, Indonesia, Japan, Korea, Malaysia, the Philippines, Thailand, and Viet Nam. A summary of the discussions, progress reports and future programs of each group are presented below.

1. Sub-Workshop Report of Tc-99m Generator Group

In the 2003 Workshop on Utilization of Research Reactors held in Serpong Indonesia, one delegate from each of China, Korea, Malaysia, the Philippines, Thailand and Viet Nam, four delegates from Japan were hosted by Indonesia to participate and promote the technology of Tc-99m generator using poly zirconium compound (PZC) as an adsorbent for neutron activated (n, γ) Mo-99.

1.1 Evaluation of the experiments conducted by each country
Following the agreement of the workshop held in Indonesia in January 2003, PZC materials have been distributed to participating countries in April, August and October 2003 from Kaken Co. The amount of PZC material sent by Kaken was 15 grams for each laboratory each time. Special distribution was done according to the request from CIAE, China. For these experiments, use of secondary column of alumina and oxidizing agent NaOCl in saline were compulsory to follow the standard protocol issued by FNCA for the elution process.
In the present sub-workshop, the results of the experiments in terms of Mo-99 adsorption, Tc-99m elution and Mo-99 breakthrough were reported and discussed to evaluate the performance of PZC based Tc-99m generator. They are summarized in the Table 1.
The comments from each country for the results are as follows.

China
(NPIC)
Two experiments with different batch of PZC with different technical process showed different quality of 99Mo-PZC generator. The adsorption process (the temperature, intensity and frequency of shaking and the PZC volume in solution etc.) can seriously affect the adsorption efficiency of 99Mo in the solution.
The adsorption efficiency of 99mMo at 90°C for 3 hours is not as high as that before, and the reason of the increase of elution yield along with the elution date in the second experiment should be ulteriorly discussed. The 99mMo-PZC generator system can be put into commercial application after further improvement of the performance of PZC.

(CIAE)
Because the PZC is breakable, there is much fine PZC powder after the Mo adsorption process. After removing the fine PZC powder and washing the PZC powder, the rate of remained 99Mo (adsorbed onto PZC powder) is about 70.0%. It is necessary to take measures to reduce the loss of 99Mo adsorbed onto the fine PZC powder and to quicken the 99mTc elution process. Further experiment will be requested.

Indonesia
Coated PZC showed adsorption capacity and 99mTc yield as high as those of PZC with better property of the 99Mo-PZC slurry.
The contents of total Mo, Zr, and Al in 99mTc solution are <0.2 ppm for Mo and <5.0 ppm for Al and Zr. The values are in agreement with the specification of clinically used 99Mo/99mTc generators.

Japan
It is concluded that PZC is applicable to a practical 99mTc generator based on natural Mo (n, gamma) 99Mo. The generator assembly is almost same as the ordinary fission type generator. Further trial of using 99Mo as high as 37 GBq (1 Ci) level is to be justified in this stage in order to realize a practical generator.

Korea
The performance of PZC distributed in 2003, although molybdate adsorption capacity decreased by 10-20%, seems to be improved in less breakthrough of 99Mo, higher material stability, better elution efficiency, etc. compared to other PZC batches. Especially, the PZC coated with TEOS seems to be suitable as an absorbent for the commercial application of 99Mo/99mTc generator.

Malaysia
Because of renovation of hot facilities in MINT, all PZC samples distributed by Kaken are kept until new facility becomes available. The PZC technology can be adopted if only the production procedure is established because changing the current alumina based column technology to PZC column requires major changing of production equipments and facilities. Issue of evaluations and registration by local drug authority is also necessary. In order to meet the local demand, irradiation service for Mo and shipment to Malaysia is required.

Philippines
The experiments on PZC showed that the coated PZC gave better elution yield than the previous uncoated batches. The adherence to the standard protocol for preparing the PZC column as 99Mo-99mTc generator is emphasized to obtain the high elution yield and low Mo breakthrough. If the PZC will be exported as column material, a study on the shelf life of the material may be needed.

Thailand
The coated PZC seemed to be a suitable material for generator preparation owing to its high molybdenum adsorption, high 99mTc elution yield and very low percentage loss of fine powder.
It is strongly believed that in the near future this technology will be established and utilized under the framework of FNCA which will benefit the countries operating small research reactors to overcome the difficulties in production of 99Mo/99mTc generator.

Viet Nam
The procedures and relevant 99mTc generator designs for the preparation of PZC based 99mTc generators were successfully set up. The columns of from 1.0 gram to 4.0 gram weight of PZC and from 200 mCi to 1000 mCi 99Mo can be used to produce portable, chromatographic type 99mTc generators which have a good performance for application in clinical investigations.
Among the established procedures the column pre-loading procedure was highly evaluated, because it proved to be prominent figures for easy and safe operation, for low cost of technology facilities and equipment and for the capability to match the traditional technology of the fission 99Mo based 99mTc generator production.

1.3 Work plan for 2004

1.3.2 Establish a high quality PZC synthesis procedure
Kaken Co. establishes strict quality control system for synthesizing PZC

1.3.3 Labeling test
Confirmation of quality of 99mTc solution obtained from PZC generator through labeling test with various radiopharmaceutical kits.

1.3.4 Distribution of PZC material
Kaken Co. distributes PZC materials to participating laboratories 3 times within fiscal year 2004 for the labeling test and other experiments related to PZC type 99mTc generator development.

1.3.5 Expert exchange for loading system development
Experts visit and stay to collaborate in further improvement of loading system installed in BATAN to share experiences of how to operate the machine. Travel and accommodation cost is, in principle, to be born by the institution of the expert.

1.3.6 Clinical trial in hospitals
BATAN conducts the clinical trials of PZC based 99mTc labeled kits under cooperation with several hospitals in Jakarta and Bandung.

1.3.7 Pre-loading system test
BATAN and other interested laboratories test the pre-loading system developed by Viet Nam using high radioactive 99Mo.

1.3.8 Publish comprehensive report
Publish the comprehensive report on PZC type 99mTc generator technology containing historical details, comparison of different types of generators, synthesis of PZC material, assembly of generator, column loading systems and reference articles etc.

1.4 Work plan for 2004

The work plans for 2004 is summarized in Table 3.

1.5 Comments and suggestions

1.6 Others

2. Expert Meeting of Neutron Scattering Experiment

2.1 Project Title
Development of Evaluation Technology of Natural and Synthetic Polymer Materials (mainly NR-TPE) using Small Angle Neutron Scattering (SANS)

Participating Countries
China, Indonesia, Japan, Malaysia, Philippines, Thailand, Vietnam

2.2 Outline
The neutron scattering project was initially proposed and adopted at the 5th Workshop of the Utilization of Research Reactors held in 1995. The calibration of SANS instrument in the stage 1 of the project and the establishment of data analysis technique using the standard polymer samples in the stage 2 were followed by the current stage 3, conduct of research and development of the natural polymers using SANS, which was accepted by the coordinators meeting held in March, 2002.
The property of polymers such as natural rubber thermoplastic elastomer (NR-TPE) and natural carrageenan (NC) produced dominantly in the member countries depends on their macroscopic and microscopic structures. Using the unique method of SANS, polymer scientists and neutron scientists cooperatively explore the relationship between the property and the nano-scaled structures of the natural polymers. The information of the relationship should become a powerful guide for the industrial application of the natural polymers. Therefore, the activities of the neutron scattering project will contribute to the socio-economic development in the member countries.

2.3 Current activities

2.3.1. Natural rubber thermoplastic elastomer
Thailand reported the strengthening linkage between the OAP, MTEC and Mahidol University to carry out the SANS experiments of the natural rubber/polyethylene blends (NR/PE). The mechanical properties of the blends were measured. Twenty-one samples were provided to professor Hasegawa in Kyoto University for the SANS-J experiments at JRR-3M. The experimental results revealed the contrast between NR/PE and carbon black, that leads to see the interface structure of these blends.
Mr. Jipawat Chamchang visited Dr. S. Koizumi of JAERI to study the structural properties of poly-trimethylene terephthalate (PTT) and poly-ethylene naphthalene (PEN) blends by SANS-J.

Vietnam reported that the research on radiation vulcanization of natural rubber latex and preparation of copolymers by grafting monomers onto natural rubber latex and/or onto other synthetic polymers have been started since 1990. In the FNCA project natural rubber thermo-plastic elastomer (NR-TPE) and copolymers have been prepared mainly by radiation cross-linking and grafting methods. The resulting products were characterized by SANS, SAXS, TEM, and thermo-mechanical and physio-mechanical measurements. The physio-mechanical properties of NR-PTE have been improved, and the thermal stability and salinity of the PVA-graft-AAM have been improved dramatically as a result of copolymer formation.

From Indonesia, Mr. Utama reported the trial production of low protein irradiated natural rubber latex in factory scale by gamma and electron beam irradiation technique. Dr. Suratno reported the effect of ultra violet light, temperature, moisture on automotive rubber bushing. Mr. Syamsu reported the development and prospects of modified natural rubber product. These reports drew strong attention of participants to the linking between the cross-linked polymer particles and the possible application of the SANS technique to observe the linkage. Dr. Ikram reported that the SANS profiles of five NR/PE samples from Thailand were obtained by using BATAN SANS instrument. The sample-to-detector distance employed was 1.5 and 10 m with the neutron wavelength of 0.4 nm. The results were comparable to the SANS data obtained with SANS-J at JAERI, Tokai, Japan. The control computer of the SANS went wrong in the middle of the measurements. He also reported that the SANS at RSG-GAS will be operated in February or March, 2004 after the repair works on the computer system and will welcome natural polymers to be investigated in the project.

Malaysia reported the effects of molecular weight of LNR, as a compatibilizer on NR/LLDPE(Linear Low Density Polyethylene) blend. Rheological studies and mechanical properties of the blend showed that the molecular weight of LNR influences the compatibility of the blend. Improvements in the mechanical properties were in agreement with the increase in gel contents of the blend. From the DSC(Differential Scanning Calorimeter) study, it has been observed that increasing LNR content decreases the melting point, Tm, and the heat of fusion, DHf, which are indicators of the crystalline part of the blend. The decrease reflects a reduction in the degree of crystallinity which is due to the interference in the form of LNR dissolution into the LLDPE phase. SEM examination further confirmed the improved compatibility of NR/LLDPE blend by LNR addition.

Professor Hasegawa reported his SANS and SAXS experiments on the provided samples from Thailand, Vietnam and Indonesia. They studied the phase-separated structures of natural rubber thermoplastic elastomers (NR-TPE) which are recyclable materials without vulcanization and consume less energy for processing than vulcanized rubbers. Therefore, NR-TPE’s are friendly to the environment and their production is expected to increase in the future. However, their structure-property relationships are not clarified yet. The main problem is that the techniques for quantitative evaluation of their structures are not established. In this study, they could show that SANS was an extremely useful technique to evaluate the thickness of the interfaces between coexisting two phases, which was strongly related to the mechanical properties of NR-TPE.

2.3.2. Carrageenan
Philippines reported that the research proposal on carrageenan was accepted to be conducted in collaboration with the Prof. M. Shibayama of ISSP-Tokyo University on the basis of the economic importance and support of the Philippine government. Two studies were proposed by the Philippines, that are structural investigation of -ray irradiated -carrageenan (KC) and structural investigation of -carrageenan/PVP blend cross linked by -irradiation.

Professor Shibayama reported that the structure and dynamics of -ray irradiated -carrageenan (KC) aqueous solutions were investigated by dynamic light scattering (DLS) and SANS as a function of irradiation dose and temperature. The DLS data showed that the intensity correlation function (ICF) shifted towards shorter relaxation times with increasing radiation dose as a result of radiolysis. The characteristic decay time distribution function (CDF), G(), indicates the presence of fast and slow mode peaks respectively at around 0.1 to 10 ms and 100 to 1000 ms. A peak broadening of the fast mode peak in G() appeared with decreasing temperature, indicating that coil-to-helical conformation transition took place. The conformation transition temperature (CTT) decreased with increasing radiation dose. No transition was observed for KC irradiated at 300 kGy. A new faster relaxation mode appeared at around 0.1 to 1 ms at temperatures below the CTT. This peak is found in KC irradiated at doses exclusively between 75 to 175 kGy. The peak height of this mode is largest at 100 kGy which corresponds to the optimum biological activity of KC reported previously. The SANS intensity from KC in deuterated water increased dramatically by gelation, indicating that conformational rearrangement, e.g., helix formation accompanying aggregation, underwent by gelation. However, no noticeable irradiation-dose dependence was observed.

2.4 Upgrade of neutron facility

China reported that the China Advanced Research Reactor (CARR) now is being built at CIAE to meet the increasing demand of neutron scattering research in China. CARR is a tank-in-pool inverse neutron trap type research reactor with nuclear power of 60 MW, and the unperturbed thermal neutron flux is 8x1014 n/cm2s. Seven out of nine tangential beam tubes are designed for neutron scattering researches. A liquid hydrogen cold source at 20 K will be installed, and 4 cold neutron guides will be used for transportation of the cold neutron beams to the guide hall. The objective of neutron scattering program on CARR is establishment of a complete set of spectrometers as the tool for neutron scattering research in the fields of life sciences, material sciences, physics, chemistry and chemical engineering, minerals, environment sciences, industrial and engineering applications et al. Therefore FNCA cooperation will also be welcome to CARR.
Dr. Morii of JAERI reported that an upgrade plan of JRR-3M was made and will be published in February 2004 by the task force under the neutron beam utilization committee held for the last two years. Upgrade of the cold source and the installation of supermirror neutron guide are strongly recommended. He also reported the capability of the Japanese spallation neutron source, JSNS, at the Japan intense Proton Accelerator research Complex (J-PARC) which will be completed in 2007. Effective intensity of the JSNS will be nearly 100 times higher than that of JRR-3M in some research area, while time averaged cold neutron intensity will be only 3-5 times high. FNCA members may be carried out as one of the instrument users and/or owners at the J-PARC in future.
Dr. Mohamed of MINT reported the recent progress of the MySANS, ‘mini’ SANS facility, and its present applications in materials science and technology research and education. The formation of Reactor Interest Group (RIG) has lead to several experimental projects with collaborative work between MINT and the local universities/research institutes.

2.5 Future program

We strongly propose the continuous research on natural polymer such as natural rubber (NR)-TPE and carrageenan in 2004 and the following years, since we have just got the first experimental results of the structure of the polymers which show that SANS is useful to understand the macroscopic properties of the polymers. We propose to have FNCA workshop 2004 to summarize the current researches and to seek future researches. The mailing list will be continuously updated to strengthen the linkage between neutron facility and the polymer researchers as end-users for the socio-economic development in the member countries.
To carry out the experiments efficiently in future, deuterated monomers need to be provided, and the exchange of the researchers between the member countries is necessary.

2.5.1. Natural rubber thermoplastic elastomer
Through the FNCA project natural rubber thermoplastic elastomer (NR-TPE) samples were provided by Thailand and Vietnam. It was proved that small-angle neutron scattering (SANS) was an excellent technique to evaluate the interfacial thicknesses of the phase-separated structures that tremendously affect the mechanical properties of not only NR-TPE but also polymer blends in general. Indonesia proved that their SANS (BATAN) was useful to measure the interfacial thicknesses of NR-TPE by showing that the obtained data on Thai samples were comparable to those measured by SANS-J (JAERI). These are good news for the participating countries and the contribution of Indonesia to the NR-TPE project through the SANS experiments of NR-TPE in BATAN is expected to increase.

(1) Proposal by Malaysia
As the third largest NR producer, diversification of NR utilization is prime activity to produce new NR-based products. NR-TPE polymer blend is a good candidate for this initiative; Polymer blend is one of the fastest growing areas of polymer technology. Blend compatibility is an important issue to be addressed in relation to industrial uses of polymer blend materials. Good physical and mechanical properties are influenced by good compatibility of the blend component materials.
LNR has been recognized as one of the compatibilizer that gives better NR-TPE polymer blend systems. Its molecular conditions and properties are influencial to this compatibility. The study of these parameters at molecular level is therefore essential. SANS has proven to be a good method to study the structure in relation to the understanding of the compatibility process. This will finally assist the good fabrication procedure of the final products of polymer blend.
We propose two projects as follows:
1. Compatibilization study of NR-TPE blend: the role of LNR.
2. Development of new compatibilizer for NR-TPE blend based on NR
In the fiscal year 2004, Malaysia will provide new samples of NR-TPE with compatibilizer for the interfacial thickness measurements by SANS. The success of this experiment will benefit the NR-TPE industries of the participating countries by providing an irreplaceable evaluation method of compatibilizer efficiency.

(2) Proposal by Indonesia
Indonesia will prepare deuterized latex and observe its particle size using BATAN-SANS machine. Study on deproteinized natural rubber will be carried out as well if necessary to suit the q range that observable by BATAN-SANS machine. Interfacial thickness is another parameter that could be also derived from SANS data measurements. In order to push the SANS-Polymer Program further, one young scientist will be sent to Japan under the financial scheme from outside source, such as Scientific Exchange Program of MEXT. It is required that the young scientist has adequate basic knowledge both in SANS and polymer fields.

(3) Proposal by Thailand
Thailand would like to propose two topics as follows.
1) NR/PE Sample:
Thailand would like to prepare the NR/PE sample with reinforcing agent such as silica for studying the structure and morphology, especially on interfacial thickness by using SANS. This NP/PE with reinforcing agent (silica) is used in the automobile part. If we understand the structure, we can produce a good NR/PE for the purpose.
2) Human Resource Development
Because most of the SANS facility existed only in few places such as JAERI, BATAN and etc., we need to send young scientist to the facilities to get practice in using and analyzing the sample that we prepared.
FNCA could conduct the 1-2 week workshop on experiment and analysis of NR/PE sample that provides the opportunity to the young scientists and engineers of the member countries as well as polymer scientists to be involved in this workshop.

(4) Proposal by Vietnam
1. Preparation of NR-TPE by radiation grafting method.
–NR-graft-PMMA blending with fillers such as clay/or wood powder
–NR-graft-polystyrene (PS)
–NR-graft- polystyrene (PS) blending with fillers as clay/or wood powder.
The samples will be prepared with different grafting degrees.
2. Preparation of copolymers by radiation-grafting methods based on polyvinyl alcohol (PVA).
-PVA-graft-PAAM with different molecular weights of PVA and grafting degrees.
-PVA-graft-PAAM blending with natural polysaccharides (CM-chitin/chitosan)
3. Evaluation of the ability of application of researched product in industry.

(2) Proposal by Japan
Japan will collaborate with the FNCA member countries for the study of the natural polymers planned in 2004. The planned SANS experiments will be carried out at SANS-J and SANS-U, although allowed neutron beam time will be limited under the highly competitive circumstances in Japan. Japan will ask Korea and Australia whether SANS at HANARO of KAERI and HIFAR of ANSTO are available for the FNCA project in accordance with their installation of a cold source at HANARO and the construction of RRR at ANSTO for the polymer science and other sciences in their countries.
JAERI will continuously pursue the study on the structure of synthetic polymers with Japanese companies using SANS-J for the socio-economic development in Japan.

Plenary session & Parallel Session
Tuesday, 13, January 2004 (Sofitel Hotel)

Schedule of
The 2003 FNCA Workshop on the Utilization of Research Reactors
January 12 – 16, 2004, Jakarta-Serpong, Indonesia

List of Participants
2003 Workshop on the Utilization of Research Reactors
Sub-workshop on Tc-99m Generator Technology and
Expert Meeting on Neutron Scattering Experiments
January 12-16, 2004 Jakarta/Serpong, Indonesia