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[en] To protect the leakage even of the irradiation FPM capsule before irradiated, some examination which can assured the capsule in good condition is needed. Once of the useful examination method is pressure submerged testing method. In order that the leakage examination by this method can be done, the design of leakage test apparatus of FPM capsule in Centre For Development of Research Reactor Technology has been done. By the design propose, the capsule condition can be assure without leakage and ready to irradiated. By the calculation and analysis performed, the design of Leakage Test apparatus of FPM capsule proposed was capable to resist of the stresses during operation. For realizing the design, of a units of Leakage test apparatus of FPM capsule needs a piece SS 304 pipe sch 40 by 6 inch in diameter, a unit of regulator completed with pressure gage, 3 pieces of SS 304 plate by 300 x 300 x 10 mm in dimension. By the leakage test apparatus of FPM capsule design, irradiation processes of FPM capsule can be done without worrying of capsule leakage ensure
Source
Endiah-Puji-Hastuti; Setiyanto; Taswanda-Taryo; Mohammad-Dhandang-Purwadi; Pinem, Surian; Tarigan, Alim; Hasibuan, Djaruddin; Kadarusmanto (Center for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)); Center for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia); 235 p; ISSN 0854-5278; 
; May 2003; p. 197-202; Seminar Result of Research Reactor Safety Technology Research Centre 2002; Seminar Hasil Penelitian P2TRR tahun 2002; Serpong (Indonesia); 4-5 Feb 2003; Also available from Centerfor Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 3 refs; 1 tab; 4 figs
; May 2003; p. 197-202; Seminar Result of Research Reactor Safety Technology Research Centre 2002; Seminar Hasil Penelitian P2TRR tahun 2002; Serpong (Indonesia); 4-5 Feb 2003; Also available from Centerfor Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 3 refs; 1 tab; 4 figs
[en] Based to the planing to measure the leak of reactor aluminium tank in Indonesia, the design of the reactor aluminium tank wall leak test tool has been done in center of Multi Purpose Reactor in Serpong. By the design purposed, the needs of leak test tools for reactor aluminium tank in Indonesia has completed. To realized the design performed the SS 316 plate by 1000 x 1000 x 1 mm, a unit of vacuum pump and flexible hoses by inner diameter d = 6.5 mm and 30 m in length is needed. By the design of reactor aluminium tank wall leak test tool, the leak test of the reactor aluminium wall tank can be done. (author)
Journal
Buletin Pengelolaan Reaktor Nuklir; ISSN 0216-2695; ; v. 3(1); p. 15-23
; v. 3(1); p. 15-23
[en] To increase the operation quality of the spent fuel transportation system to ISFSF building, the design modification of the system has been done. By that design, the operation of the system will be out of the difficulties of use. The design system requires an unit of electric motor of 0.25 K W and one pieces of jowls steel plate by 1,000 x 1,000 x 5 mm as power transmission system and take over bridge
Source
Endiah-Puji-Hastuti; Setiyanto; Taswanda-Taryo; Mohammad-Dhandang-Purwadi; Pinem, Surian; Tarigan, Alim; Hasibuan, Djaruddin; Kadarusmanto (Center for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)); Center for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia); 235 p; ISSN 0854-5278; ; May 2003; p. 219-223; Seminar Result of Research Reactor Safety Technology Research Centre 2002; Seminar Hasil Penelitian P2TRR tahun 2002; Serpong (Indonesia); 4-5 Feb 2003; Also available from Centerfor Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs; 3 figs
; May 2003; p. 219-223; Seminar Result of Research Reactor Safety Technology Research Centre 2002; Seminar Hasil Penelitian P2TRR tahun 2002; Serpong (Indonesia); 4-5 Feb 2003; Also available from Centerfor Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs; 3 figs
[en] To know the ageing rate process of the research reactor in Indonesia, a method of main mechanical component evaluation of research reactor according to the ASME code, ASTM, ANSI B31.1 has been composed. This evaluation method will discuss the main component identification, determination of ageing stress, detail arrangement of the fault mechanism possibility, inspection and analyzed done. This paper is made base on the experience during attending of NTC on Ageing Management of Research Reactor. By this systematical evaluation, the application of evaluation will easily to be done. (author)
Journal
Buletin Pengelolaan Reaktor Nuklir; ISSN 0216-2695; ; v. 2(2); p. 88-95
; v. 2(2); p. 88-95
[en] The rabbit transfer system facility is a facility that a function to decrease the transfer times of the irradiated samples from isotop cell to counting room. Base on the planning to increase the research activity and the service quality to the rabbit system user's is necessary to realized manufacturing and installation of the mention facility. The detail design purpose needs 35 m length of polypinil hose by 36 mm inner diameter and 42 mm outer diameter. By doing analysis the transfer time needs to move the sample is 3 seconds. As a reference use ASME, ASTM and AISC standard
Source
Setiyanto; Purwadi, M. Dhandhang; Pinem, Surian; Sitorus Pane, Yupiter; Kuntoro, Iman; Puji Hastuti, Endiah; Simanjuntak, Anthony; Tarigan, Alim; Hasibuan, Djarudin; Djunaidi (National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Reactor Safety Technology Research Center, National Nuclear Energy Agency, Serpong (Indonesia); 232 p; ISSN 0854-5278; ; Feb 2001; p. 27-33; Seminar Result of Research Reactor Safety Technology Research Centre 2000; Seminar Hasil Penelitian P2TRR Tahun 2000; Serpong (Indonesia); 27-28 Feb 2001; Also available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 6 refs.; tabs.; 5 figs.
; Feb 2001; p. 27-33; Seminar Result of Research Reactor Safety Technology Research Centre 2000; Seminar Hasil Penelitian P2TRR Tahun 2000; Serpong (Indonesia); 27-28 Feb 2001; Also available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 6 refs.; tabs.; 5 figs.
[en] Base on planning to increase of the irradiation service quality in Multi purpose Reactor-GAS, the mechanical design and manufacturing of the (n,γ) irradiation facility has been done. The designed of (n,γ) irradiation facility is a new facility in Multi purpose Reactor-GAS. The design doing by design of stringer, guide bar and hanger. By the design installation, the continuous irradiation service of non fission reaction will be easy to be done without reactor shut down. The design of the facility needs 3 pieces Al pipe by 36 x 1.5 mm, a peace of Al round bar by 80 mm diameter and a piece of Al plate by 20 x 60 x 0.2 mm for the stringer and guide bar manufacturing. By the building of non fission irradiation facility in the reflector irradiation position, will make the irradiation service to be increased. (author)
Source
Endiah Puji Hastuti; Setiyanto; Taswanda Taryo; Mohammad Dhandhang Purwadi; Pinem, Surian; Tarigan, Alim; Hasibuan, Djaruddin; Kadarusmanto; Amir Hamzah (Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia); 288 p; ISSN 0854-5278; ; May 2004; p. 67-72; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 1 tab.; 1 fig.
; May 2004; p. 67-72; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 1 tab.; 1 fig.
[en] Base on the planning to increase of the research and service quality in the ''Neutron activation analysis'' (APN),the design of mentioned ''Neutron activation analysis laboratories room'' has been done in the multi purpose reactor G.A. Siwabessy. By the using the designed installation, the irradiation preparation and counting sample can be done. The design doing by determination of installation lay out and maximum particle contain in the air. The design installation required a unit of 1 HP blower, a unit of 1 HP split air condition and 2 units 1200 x 800 mm HEPA filter. This paper concluded that this design is feasible to fabricated
Source
Purwadi, M. Dhandhang; Setiyanto; Taryo, Taswanda; Sitorus Pane, Yupiter; Kuntoro, Iman; Puji Hastuti, Endiah (National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Reactor Safety Technology Research Center, National Nuclear Energy Agency, Serpong (Indonesia); 144 p; ISSN 0854-5278; ; Jun 2000; p. 31-35; Seminar Result of Research Reactor Safety Technology Research Centre 1999/2000; Seminar Hasil Penelitian P2TRR Tahun 1999/2000; Serpong (Indonesia); 30-31 May 2000; Also available from from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 3 refs.; 1 tabs.; 2 figs.
; Jun 2000; p. 31-35; Seminar Result of Research Reactor Safety Technology Research Centre 1999/2000; Seminar Hasil Penelitian P2TRR Tahun 1999/2000; Serpong (Indonesia); 30-31 May 2000; Also available from from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 3 refs.; 1 tabs.; 2 figs.
[en] One of the technical problem when the RSG-GAS reactor operated at the high power level is the decreasing of the pressure level in the primary cooling system as function of operation time. Some preceding research concurred that this problem caused by the accumulation of the air or gas in the upper part of delay chamber, but the source of these gas still not defined yet. It was predicted that the gas accumulation were come from cavitations or radiolysis phenomena. To solve this problem, the research was realized by investigating of the pressure in the primary cooling system, with or without reactor operation. The investigation without reactor operation related to the cavitations phenomena, while investigation in reactor power will get some information related to the effect radiolysis in water. The results obtained showed that the pressure decreasing in the primary cooling system was only occurred if the reactor is operated. It can be concluded that the cavitations not occur in the primary cooling system. So the air accumulation has make water decreasing in the delay chamber came from the radiolysis in the reactor core. (author)
Journal
Jurnal Teknologi Reaktor Nuklir; ISSN 1411-240X; ; v. 7(2); p. 68-75
; v. 7(2); p. 68-75
[en] The samples transfer of rabbit system, has been built in the Reactor Serba Guna G.A. Siwabessy building. The erection of the samples transfer of rabbit system, doing by started of preparation the Manufacturing procedure refer to Final design of the facility of rabbit system transfer. Manufacturing process and erection doing refer to procedures makes. By providing of the Samples transfer of rabbit system can be concluded that the research activity and users services in P2TRR well meet to be done. (author)
Source
Endiah Puji Hastuti; Setiyanto; Taswanda Taryo; Mohammad Dhandhang Purwadi; Pinem, Surian; Tarigan, Alim; Hasibuan, Djaruddin; Kadarusmanto; Amir Hamzah (Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Centre for Development of Research Reactor Technology, National Nuclear Energy Agency, Serpong (Indonesia); 288 p; ISSN 0854-5278; ; May 2004; p. 59-66; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 3 figs.
; May 2004; p. 59-66; Seminar on Research Result of Research Reactor Technology Centre 2003; Seminar Hasil Penelitian P2TRR Tahun 2003; Serpong (Indonesia); 24-25 Feb 2004; Also available from Center for Development of Nuclear Informatics, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 4 refs.; 3 figs.
[en] The ''NAA laboratory clean room'' has been built in the Reactor Serba Guna G.A. Siwabessy building. The erection of ''AAN laboratory clean room'' doing by started of preparation of the ''manufacturing procedure'' refer to ''Design and manufacturing neutron activation analysis clean room laboratory''. Manufacturing process and erection doing refer to procedures makes. By providing of the ''AAN laboratory clean room'' can be cocluded that the research activity and the user sevises in P2TRR well meet to be done
Source
Setiyanto; Purwadi, M. Dhandhang; Pinem, Surian; Sitorus Pane, Yupiter; Kuntoro, Iman; Puji Hastuti, Endiah; Simanjuntak, Anthony; Tarigan, Alim; Hasibuan, Djarudin; Djunaidi (National Nuclear Energy Agency, Serpong (Indonesia)) (eds.); Reactor Safety Technology Research Center, National Nuclear Energy Agency, Serpong (Indonesia); 232 p; ISSN 0854-5278; ; Feb 2001; p. 1-5; Seminar Result of Research Reactor Safety Technology Research Centre 2000; Seminar Hasil Penelitian P2TRR Tahun 2000; Serpong (Indonesia); 27-28 Feb 2001; Also available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 5 refs.; tabs.; 1 figs.
; Feb 2001; p. 1-5; Seminar Result of Research Reactor Safety Technology Research Centre 2000; Seminar Hasil Penelitian P2TRR Tahun 2000; Serpong (Indonesia); 27-28 Feb 2001; Also available from Center for Development of Informatics and Computation Technology, National Nuclear Energy Agency, Puspiptek Area, Fax. 62-21-7560923, PO BOX 4274, Jakarta (ID); 5 refs.; tabs.; 1 figs.
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