Pangandaran district is a district that has the third largest coconut tree plantation area in West Java, and coconut is made as one of the potential regional prime commodities. This research objective was to discover four aspects on coconut agroindustry, namely the availability of raw material, distribution, product's prospective, and economic empowerment of society. The method used in this research was descriptive method, while survey and questionnaire spreading were used. To find out the potential availability of raw materials, secondary data were used,which were proceeded with forecasting moving average method. Spreading of coconut agroindustry was mapped for several sub-districts, according to primary or secondary data. Determination of prospective product were done by Technique for Order Performance of Similarity to Ideal Solution (TOPSIS). Potential of economic empowerment was obtained by analysis of profit cost ratio. Refer to the research results, coconut agroindustry had big potential in empowerment of the social economy. This potency can be seen by the amount of availability and certainty of coconut as raw material, the quality of the resulting coconut, availability of human resources, breadth of market section, infrastructure and means of transportation, supporting by local people, then government policy that supporting in growth and development of coconut agroindustry. The coconut agroindustry was spread in a whole sub-disctrict, and the most of it was located in Cimerak Sub-District. The most prospective product was coconut sugar, that is one of products that have big potential and profitable for empowerment of the social economy.

PEMBUATAN RADIONUKLIDA MOLIBDENUM-99 (99Mo) HASIL AKTIVASI NEUTRON DARI MOLIBDENUM ALAM UNTUK MEMPEROLEH TEKNESIUM-99m (99mTc). Pembatasan penggunaan uranium sebagai target untuk produksi 99mTc menyebabkan rumah sakit di Indonesia  kesulitan mendapatkan pasokan 99mTc. Saat ini 99mTc diperoleh dari 99Mo hasil fisi (pembelahan uranium).  Pembuatan radionuklida 99Mo dari aktivasi neutron  molibdenum alam (MoO3) di teras reaktor G.A Siwabessy digunakan sebagai metode alternatif untuk memperoleh 99mTc. Tujuan penelitian ini adalah untuk melakukan pembuatan radionuklida 99Mo dari aktivasi neutron molibdenum alam untuk memperoleh 99mTc. Serbuk MoO3 alam sebanyak 5 gram dikemas dalam ampul kuarsa dan dimasukkan ke dalam inner capsul selanjutnya dikemas menggunakan outer capsul sebagai bahan target. Bahan target diiradiasi di reaktor G.A Siwabessy selama 100 jam. Hasil perhitungan diperoleh aktivitas  99Mo sebesar 65 % dari nilai maksimum yang dapat diperoleh. MoO3 paska iradiasi dilarutkan dengan NaOH 4 M sehingga diperoleh larutan natrium molibdat (Na2MoO4). Radionuklida 99Mo dan 99mTc diukur menggunakan spektrometer gamma. Radionuklida 99Mo terdeteksi dalam produk larutan  Na2MoO4 dengan  aktivitas jenis 99Mo yang diperoleh sebesar 0,81 Ci 99Mo/g Mo.  Radionuklida anak luruh 99mTc dipisahkan dari radionuklida induk 99Mo menggunakan kolom pemisah yang berisi material berbasis zirkonium (MBZ) sebagai penyerap 99Mo. Radionuklida 99mTc hasil pemisahan diperoleh dalam bentuk natrium pertehnetat (Na99mTcO4).dengan recovery yang masih rendah yaitu sekitar 52 hingga 71 %.Kata kunci: Molibdenum, teknesium, radionuklida, pemisahan, iradiasi. PRODUCTION OF ACTIVATED  NEUTRON MOLYBDENUM-99 (99Mo) RADIONUCLIDE FROM NATURAL MOLYBDENUM TO OBTAIN TECHNETIUM-99m (99mTc).  Uranium usage restriction causes the hospitals in indonesia difficult to obtain the suply of  99mTc. At Present, 99mTc is obtanied from molybdenum as a uranium fission product. Production of 99Mo radionuclide resulted from neutron activated natural molybdenum (MoO3) in G.A Siwabessy reactor could be used  as a alternatif method for producing 99mTc. The aim of this research is synthesize of   99Mo radionuclide from neutron activated natural molybdenum  (MoO3) to obtain 99mTc. The five grams of  MoO3 powder was packed in a quartz ampule and inserted into inner capsule then also inserted into outer capsule as a target material. It was iradiated in G.A Siwabessy reactor for 100hours. Based on theoritical calculation, about 65 % of maximum 99Mo activity could be recovered. After Irradiation,  MoO3 was dissolved by NaOH 4 M solution so it was natrium molybdate (Na2MoO4) solution. 99Mo and 99mTc radionuclide were analyzed using gamma spectrometer. 99Mo radionuclide was detected on Na2MoO4 solution as product that had specific activity of 0.81 Ci 99Mo/ g Mo. 99mTc as daughter radionuclide was separated from 99Mo as parent radionuclide using separated column containing zirconium based material (ZBM) as 99Mo adsobent. 99mTc radionuclide has been succesfully separated using ZBM column although recovery of 99mTc  was quite low in which approximately 52 to 71 %. The 99mTc radionuclide was recovered in the form of sodium pertechnetate (NaTcO4) solution.Keywords: Molybdenum, technetium, radionuclide, separation, irradiation.

The aim of this paper is to discusse the concept of a marriage agreement in the Compilation of Islamic Law. This study is literature review research with a qualitative methods. The  data was gathered through content analysis and written material. Data analysis was analyzed using grounded theory approach and thematic building. The result of research shows basically, there is no difference between the Marriage Law and the Islamic Law Compilation regarding the marriage agreement. Second, the legal consequences of the marriage agreement made by each party—husband and wife, are binding. Therefore, if a violation occurs, each party can take legal action.

The fission-product 99 Mo, having a high specific activity, is commonly used in alumina-based 99 Mo /99m Tc generator. Due to the limitation on the use of fissionproduct 99 Mo, an alternative route for 99 Mo production, namely activation of natural molybdenum using thermal neutron, has been explored. Unfortunately, this neutronactivated 99 Mo has a low specific activity. Therefore, 99 Mo /99m Tc generator based on neutron-activated 99 Mo requires a column with higher capacity absorbent. Thus, in this study, the nanomaterial of alumina (nano--Al2O3) was synthesized which was expected to have a higher 99 Mo adsorption capacity, so that nano--Al2O3 could be potentially used as a matrix of column for 99 Mo/ 99m Tc generator based on neutron-activated 99 Mo. Nano--Al2O3 was synthesized by using sol-gel method and characterized using FTIR spectroscopy, X-ray diffraction (XRD), and transmission electron microscopy (TEM). In addition, the Scherrer method was used to determine the size of the crystals. To determine the 99 Mo adsorption capacity of the synthesized nanoalumina, the nano--alumina was soaked in nitric acid solution for one hour at room temperature followed by removing the filtrate. Then, the nano--alumina was soaked in 99 Mo solution (Na2 99 MoO4) at certain conditions. The FTIR spectra for nano--alumina showed adsorption peak at 450-500 cm -1 which indicated the presence of Al-O bond. The XRD patterns of nanoalumina crystals showed peaks at 2θ region of 25.8°, 35.9°, 38°, 52.8°, and 57.7°, indicating that the synthesized alumina had an α-phase with an average crystal size of ~5.5 nm. The average 99 Mo adsorption capacity of the synthesized alumina was 47.55 ± 12.3 mg Mo/g nano--Al2O3.

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