proceedings:2013_igorr15
Differences
This shows you the differences between two versions of the page.
| Both sides previous revisionPrevious revisionNext revision | Previous revision | ||
| proceedings:2013_igorr15 [2023/12/28 08:27] – add headline Joerg Pulz | proceedings:2013_igorr15 [2023/12/29 06:55] (current) – datatables Joerg Pulz | ||
|---|---|---|---|
| Line 1: | Line 1: | ||
| ===== 2013, Daejeon - South Korea ===== | ===== 2013, Daejeon - South Korea ===== | ||
| - | ^ Title ^ Author(s) ^ | + | < |
| - | | PERIODIC SAFETY REVIEW OF JSI TRIGA MARKII AND INSPECTION OF THE REACTOR | A. JAZBEC, L. SNOJ, B. SMODIS, A. LESNJAK | | + | ^ Title |
| - | | CURRENT STATUS OF JRR-3 | MASAMI KINASE*, MASAJI ARAI and TAKESHI MARUO | | + | | {{ : |
| - | | REPLACEMENT OF HANARO NEUTRON DETECTOR | SEUNG GYU DOO*, YEONG SAN CHOE, MIN WOO LEE, HYUNG KYOO KIM | | + | | {{ : |
| - | | The present status of HANARO radiation monitoring system and trend investigation | + | | {{ : |
| - | | CHARACTERISTICS OF HVAC SYSTEM IN RADIOISOTOPE PRODUCTION FACILITY | MUN LEE*, M.J. KIM, B.J. YOON, D.W. YOUN, H.S. JUNG | | + | | {{ : |
| - | | Study of different types of underwater measurement methods of physical shape of inner shell for JRTR | ABDULLAH S. AL-SINJLAWI* YEONG-GARP CHO, JONG-HA CHUNG | | + | | {{ : |
| - | | ETRR-2 OFFSITE POWER SUPPLY RELIABILITY WITH CONSEQUENCES OF MOMENTARY FAILURE | Mahmoud Gad | | + | | {{ : |
| - | | OPERATIONAL EXPERIENCE ON AGEING MANAGEMENT AT THE TRIGA RESEARCH REACTOR OF LENA (Laboratory of Applied Nuclear Energy) - University of Pavia (Italy) - | + | | {{ : |
| - | | IMPLEMENTATION OF RESEARCH REACTOR AGEING MANAGEMENT PROGRAMME AT KINR WWR-M REACTOR | OLEKSII DIAKOV | | + | | {{ : |
| - | | RECENT STATUS RSG-GAS AGEING MANAGEMENT | Geni Rina SUNARYO, Setianto, Alim TARIGAN and Djarot S WISNUBROTO | | + | | {{ : |
| - | | MATERIALS SURVEILLANCE PROGRAM FOR THE RA10 RESEARCH REACTOR | Raul Antonio Versaci | | + | | {{ : |
| - | | EXPERIENCE ON MAINTENANCE OF THAI RESEARCH REACTOR “SMALL-POOL” SECTION | C. TIPPAYAKUL | | + | | {{ : |
| - | | REGULATORY APPROACH TO SAFETY OF LONG TIME OPERATING RESEARCH REACTORS IN RUSSIA | ALEXANDER SAPOZHNIKOV | | + | | {{ : |
| - | | Engineering change management during replacement and upgradation | + | | {{ : |
| - | | REFURBISHMENT AND MODERNISATION OF PUSPATI TRIGA REACTOR: LESSONS LEARNT | Z. MASOOD, M. F. ZAKARIA, I.A. HUSSIN | | + | | {{ : |
| - | | MAJOR REFURBISHMENT OF THE UNIVERSITY OF FLORIDA TRAINING REACTOR | + | | {{ : |
| - | | REFURBISHMENT OF THE SAFETY SYSTEM AT THE CROCUS REACTOR | G. Girardin, P. Frajtag, L. Braun, A. Pautz | | + | | {{ : |
| - | | OPAL COLD NEUTRON GUIDE IN-PILE REPLACEMENT | T. ROWNES, A. ELTOBAJI, M. BELL, F.KLOSE | | + | | {{ : |
| - | | AGEING MANAGEMENT AND PREVENTIVE MEASURES FOR REACTOR POOL LINER AND BEAM TUBES AT THE DALAT RESEARCH REACTOR | NGUYEN NHI DIEN, NGUYEN MINH TUAN AND TRANG CAO SU | | + | | {{ : |
| - | | BR2: 50 YEARS AND STILL GOING STRONG | E. Koonen | | + | | {{ : |
| - | | AGEING MANAGEMENT OF BERYLLIUM AND GRAPHITE BLOCKS IN RESEARCH REACTOR MARIA | A. GOŁĄB | | + | | {{ : |
| - | | IAEA COORDINATED RESEARCH PROJECT ON THE ESTABLISHMENT OF A MATERIAL PROPERTIES DATABASE FOR IRRADIATED CORE STRUCTURAL COMPONENTS FOR CONTINUED SAFE OPERATION AND LIFETIME EXTENSION OF AGEING RESEARCH REACTORS | A. BORIO DI TIGLIOLE, D.V.H. RAO, A. ZEMAN, B. VAN DER SCHAAF, Y. BARNEA, E. BRADLEY, C. MORRIS, A. SHOKR | | + | | {{ : |
| - | | AGEING MANAGEMENT EXPERIENCE AT NUR REACTOR | S. MELLAL, A. AMEUR, R. ZAMOUN and M. REZIG | | + | | {{ : |
| - | | DESIGN OF A SAFETY MODULAR CONTROL SYSTEM FIRST IMPLEMENTED FOR THE REASSESMENT OF OSIRIS IRRADIATION DEVICES | J.-S. ZAMPA, E MAUDOUIT, V SILVA | | + | | {{ : |
| - | | REPORT ON THE REPAIR OF THE OPAL NEUTRON BEAM TRANSPORT SYSTEM | STEWART PULLEN, GENE DAVIDSON, STEVEN PANGELIS, FRANK KLOSE AND SHANE KENNEDY | | + | | {{ : |
| - | | LIFE CYCLE MANAGEMENT AT THE HIGH FLUX ISOTOPE REACTOR | Y.S. KWON, M.A. LINN, E.L.GRIFFIS, | + | | {{ : |
| - | | AGEING MANAGEMENT OF AG3NET NEUTRON BEAM TUBES IN ORPHEE RESEARCH REACTOR | F. GUPTA, M. CORBEL | | + | | {{ : |
| - | | AGEING MANAGEMENT PROGRAM OF HANARO FOR CONTINUOUS OPERATION | H.K. KIM, J.S. SHIN, Y.S. CHOI, H.S. JUNG, J.H. LEE | | + | | {{ : |
| - | | PULSTAR Reactor Power Upgrade from 1- to 2-MWth | Ayman I. Hawari | | + | | {{ : |
| - | | AGEING MANAGEMENT AND REFURBISHMENT OF GHANA RESEARCH REACTOR-1(GHARR-1) | E. O. AMPONSAH-ABU, | + | | {{ : |
| - | | Modification and Continue Monitoring of Kartini Reactor Tank Liner for Long Term Safe Operation | Puradwi I.W, S.Nitiswati, | + | | {{ : |
| - | | AGEING MANAGEMENT AND REFURBISHMENT OF RESEARCH REACTOR CIRUS | RAKESH RANJAN & R. C. SHARMA | | + | | {{ : |
| - | | THE NNR REQUIREMENTS TO ADDRESS MODIFICATION, | + | | {{ : |
| - | | NIST REACTOR SOLVES OPERATIONAL NUISANCE PROBLEM USING NOVEL APPLICATION OF VACUUM TRANSFER TECHNOLOGY | P.C. BRAND, A.J. NORBEDO, G.S. SPRENGER | | + | | {{ : |
| - | | A systematic programme for ageing management of research reactors | Deshraju Rao and Edward Bradley | | + | | {{ : |
| - | | REFURBISHMENT, | + | | {{ : |
| - | | REDUCTION IN SIZE OF BOTTOM-MOUNTED REACTIVITY CONTROL MECHANISM OF RESEARCH REACTOR FOR SEISMIC QUALIFICATION TEST | JONG-OH SUN, GYEONGHO KIM, YEON-SIK YOO, YEONG-GARP CHO, JONG-IN KIM | | + | | {{ : |
| - | | A LONG-TERM COOLING METHOD FOR A RESEARCH REACTOR | K.Y. LEE , S.H. KIM, J. YOON | | + | | {{ : |
| - | | Influence of single-phase heat transfer correlations on safety analysis of research reactors with narrow rectangular fuel channels | A. Rawashdeh, B. Lee, Y.J. Chung, S. Park, R. Altamimi | | + | | {{ : |
| - | | A FULLY RECONSTITUTED SAFETY BASIS FOR THE UNIVERSITY OF FLORIDA TRAINING REACTOR | K.A. JORDAN, D. SIEFMAN AND D. CRONIN | | + | | {{ : |
| - | | COMPLEMENTARY SAFETY ASSESSMENTS FOR RESEARCH REACTORS FOR THE FRENCH NUCLEAR SAFETY AUTHORITY | C. KASSIOTIS, A. RIGAUD, L. EVRARD | | + | | {{ : |
| - | | CRITICALITY CALCULATIONS FOR A TYPICAL NUCLEAR FUEL FABRICATION PLANT WITH LOW ENRICHED URANIUM | H.A. ElSAYED, M.K. SHAAT, M.E. NAGY, S.A. AGAMY | | + | | {{ : |
| - | | MAJOR UPDATE OF SAFETY ANALYSIS REPORT FOR THAI RESEARCH REACTOR-1/ | + | | {{ : |
| - | | THE PERIODIC SAFETY REVIEW OF ANSTO’S OPAL REACTOR | MARK SUMMERFIELD | | + | | {{ : |
| - | | STUDY ON OPTIMIZATION OF I&C ARCHITECTURE FOR RESEARCH REACTORS USING BAYESIAN NETWORKS | RAHMAN KHALIL UR, JINSOO SHIN, GYUNYOUNG HEO | | + | | {{ : |
| - | | MODEL BASED CYBER SECURITY ANALYSIS FOR RESEARCH REACTOR PROTECTION SYSTEM | JINSOO SHIN, RAHMAN KHALIL UR, GYUNYOUNG HEO, HANSEONG SON | | + | | {{ : |
| - | | DETERMINISTIC ANALYSIS OF A BEYOND DESIGN BASIS ACCIDENT IN A LOW POWER, PIN-TYPE FUEL RESEARCH REACTOR | H. ABDOU, D. DELBIANCO, J GONZÁLEZ, V. GAREA | | + | | {{ : |
| - | | SAFE OPERATION OF THE NRU RESEARCH REACTOR NOW AND BEYOND 2021 | S. MISTRY | | + | | {{ : |
| - | | SAFETY RE-EVALUATION OF KYOTO UNIVERSITY RESEARCH REACTOR BY REFLECTING THE ACCIDENT OF FUKUSHIMA DAIICHI NUCLEAR POWER PLANT | K. NAKAJIMA, T.YAMAMOTO | | + | | {{ : |
| - | | IAEA INTERNATIONAL CENTRES BASED ON RESEARCH REACTORS (ICERR): A NEW INITIATIVE TO SUPPORT AND ASSIST MEMBER STATES EMBARKING IN NUCLEAR PROGRAMMES | Andrea Borio di Tigliole | | + | | {{ : |
| - | | DESIGN REQUIREMENTS FOR SMALL REACTOR FACILITIES IN CANADA (FOCUS ON DIFFERENCES FROM THOSE FOR NPPs) | SANG SHIM | | + | | {{ : |
| - | | PLANNING AND IMPLEMENTATION OF A TC PROJECT FOR ACQUISITION OF A NEW RESEARCH REACTOR FOR MULTIPURPOSE APPLICATIONS IN NIGERIA | F.E. OSAISAI, E.D. MSHELIA, L.A. DIM, S.A. JONAH | | + | | {{ : |
| - | | Developing a framework for a sustainable research reactor program in the UAE | Khalid Almarri | | + | | {{ : |
| - | | THE JULES HOROWITZ REACTOR : A NEW HIGH PERFORMANCES EUROPEAN MTR (MATERIAL TESTING REACTOR) WITH MODERN EXPERIMENTAL CAPACITIES : TOWARD AN INTERNATIONAL USER FACILITY | G. BIGNAN, J. ESTRADE | | + | | {{ : |
| - | | JULES HOROWITZ REACTOR: ORGANISATION FOR THE PREPARATION OF THE COMMISSIONING PHASE AND NORMAL OPERATION | J. ESTRADE, J.L. FABRE, O. MARCILLE | | + | | {{ : |
| - | | IAEA GUIDELINES FOR NEW RESEARCH REACTOR PROJECTS | A. BORIO DI TIGLIOLE, E. BRADLEY, P. ADELFANG, Y. BARNEA, T. HARGITAI, H. ABOU-YEHIA, A. SHOKR | | + | | {{ : |
| - | | Status of Jordan Research and Training Reactor Project | Soo-Youl Oh | | + | | {{ : |
| - | | New Research Reactor Project in Korea | S. WU, J.S. SONG, T.H. KWON, J. Y. KIM, I.C. LIM, J.J. HA | | + | | {{ : |
| - | | STUDY OF THE EFFECT OF PH, SURFACE FINISH AND THERMAL TREATMENT ON THE CORROSION OF ALFENI ALUMINUM ALLOY | D. NABHAN, B. KAPUSTA, P. BILLAUD, C. PASGRIMAUD, J.P. GOZLAN | | + | | {{ : |
| - | | Nuclear research reactors activities in INVAP | Juan Pablo Ordoñez | | + | | {{ : |
| - | | Development Plan and R&D Status of China Lead-based Reactor | Yican Wu, Yunqing Bai, Yong Song, Yazhou Li, and FDS Team | | + | | {{ : |
| - | | JULES HOROWITZ REACTOR PROJECT FUEL IRRADIATION DEVICE INNOVATIVE INSTRUMENTATION PROPOSAL FOR EXPERIMENTAL PHENOMENA REAL TIME MEASUREMENT. | S.GAILLOT, G.CHEYMOL | | + | | {{ : |
| - | | UTILIZATION OF THE TRIGA RESEARCH REACTOR OF THE UNIVERSITY OF PAVIA | A. SALVINI, D. ALLONI, R. CREMONESI, G.MAGROTTI, S. MANERA, M. ODDONE, M. PRATA | | + | | {{ : |
| - | | EDUCATION AND TRAINING ON ISIS RESEARCH REACTOR | F. FOULON, G. BADEAU, B. LESCOP, X. WOHLEBER | | + | | {{ : |
| - | | Neutron beam applications for stress and deformation research in engineering materials | Wanchuck Woo | | + | | {{ : |
| - | | RESEARCH, EDUCATION AND SERVICE UTILIZATIONS OF BREAZEALE NUCLEAR REACTOR AT THE RADIATION SCIENCE AND ENGINEERING CENTER AT THE PENNSYLVANIA STATE UNIVERSITY | K. ÜNLÜ, B. HEIDRICH | | + | | {{ : |
| - | | NEUTRON SCATTERING FACILITIES AT THE OAK RIDGE NATIONAL LABORATORY HIGH FLUX ISOTOPE REACTOR | + | | {{ : |
| - | | CURRENT STATUS AND PROSPECT OF RESEARCH REACTOR UTILIZATION IN KOREA | I.C. LIM, H.S. JUNG, K.H. LEE, S.J. PARK, M.H. KIM | | + | | {{ : |
| - | | INTERNET REACTOR LAB FOR DISTANCE EDUCATION AND TRAINING IN NUCLEAR FIELD | SEUNGYONG PARK, CHARY RANGACHARYULU, | + | | {{ : |
| - | | HANARO Neutron Radiography Facility and Fuel Cell Research | TaeJoo Kim | | + | | {{ : |
| - | | DESIGN AND DEVELOPMENT OF FAST PNEUMATIC TRANSFER SYSTEM (PTS) FOR INSTRUMENTAL NEUTRON ACTIVATION ANALYSIS AT JORDAN RESEARCH REACTOR | Y.S. CHUNG, S.H. KIM, J.H. MOON, J.B. CHOI, J.M. LEE, J.S. RYU | | + | | {{ : |
| - | | MEASUREMENT OF THERMAL NEUTRON BEAM PARAMETERS IN THE LVR-15 RESEARCH REACTOR | L. VIERERBL, J. ŠOLTÉS, M. VINŠ, Z. LAHODOVÁ, V. KLUPÁK | | + | | {{ : |
| - | | RECTIFICATION OF THE OPAL COLD NEUTRON SOURCE CRYOGENIC SYSTEM | WEIJIAN LU | | + | | {{ : |
| - | | A LIQUID DEUTERIUM COLD NEUTRON SOURCE FOR THE NIST RESEARCH REACTOR – CONCEPTUAL DESIGN | R. E. Williams, M. Middleton, P. Kopetka, J. M. Rowe and P. C. Brand | | + | | {{ : |
| - | | PRODUCTION OF RADIOISOTOPES ON THE JULES HOROWITZ REACTOR | J.-P. COULON, M. ANTONY, G. MARTIN, S. GAY | | + | | {{ : |
| - | | NEUTRONIC AND THERMAL HYDRAULIC ANALYSES OF IRRADIATED FUEL PLATES FOR MOLYBDENUM-99 PRODUCTION | Daeseong Jo, Hong-Chul Kim, Kyung-Hoon Lee, Jonghark Park, Heetaek Chae | | + | | {{ : |
| - | | Development of a Calibration System for Dosimetry and Radioactivity of Beta-Emitting Sources | CHANG HEON CHOI. SUNG-JOON YE, KWANG-JAE SON. Ul JAE PARK | | + | | {{ : |
| - | | Progress in Establishment of Fission Mo Production Technology in Korea | Jun Sig Lee | | + | | {{ : |
| - | | NUCLEAR REACTORS AND PRODUCTION OF MEDICAL RADIOISOTOPES: | + | | {{ : |
| - | | DESIGN CONCEPT OF KIJANG RESEARCH REACTOR FOR NEUTRON TRANSMUTATION DOPING OF 300 MM INGOTS | B.J. JUN, H.S. KIM. C.G. SEO, H.C. KIM AND B.C. LEE | | + | | {{ : |
| - | | NTD SILICON; PRODUCT CHARACTERISTICS, | + | | {{ : |
| - | | DEVELOPMENT OF TOOLS FOR TREATING AN IRRADIATED FUEL ROD ASSEMBLY IN THE POOL OF HANARO | J.T. HONG, S.H. AHN, K.H. KIM, C.Y. JOUNG | | + | | {{ : |
| - | | Radiation induced growth of zirconium alloy in research reactor | Sang Il Choi, Jun hyun Kwon, Gyeong-Geun Lee and Ji Hyun Kima | | + | | {{ : |
| - | | Fuel and material irradiation hosting systems in the Jules Horowitz Reactor | C. BLANDIN*, J. ESTRADE, C. COLIN, T. DOUSSON, L. FERRY, J. PIERRE, P. ROUX, C. GONNIER | | + | | {{ : |
| - | | Radiation Damage of Beryllium Reflector for Research ApplicationReactor | + | | {{ : |
| - | | Development of a Low Temperature Irradiation Capsule for Research Reactor Materials | Kee Nam CHOO, Man Soon Cho, Cheol Yong Lee, Sung Woo Yang, Yoon Taek Shin, Seng Jae Park, Suk Hoon Kang, Young Hwan Kang and Sang Jun Park | | + | | {{ : |
| - | | COMMERCIAL APPLICATIONS AT FRM II BASED ON NEUTRON IRRADIATIONS | H. GERSTENBERG, | + | | {{ : |
| - | | Status on the Development of High-Temperature Irradiation Technology for a Future Nuclear System in HANARO | MAN SOON CHO, KEE NAM CHOO, SEONG WOO YANG, SEONG TAEK HONG, YOUNG HWAN KANG, SANG JUN PARK | | + | | {{ : |
| - | | THE FUTURE UNDERWATER NEUTRON IMAGING SYSTEM OF THE JULES HOROWITZ MTR: AN EQUIPMENT IMPROVING THE SCIENTIFIC QUALITY OF IRRADIATION PROGRAMS | D. PARRAT, P. GUIMBAL, G. LE GUILLOU, E. SIMON, L. BOUCHER, | + | | {{ : |
| - | | FLUORIDE SALT HIGH TEMPERATURE Reactor Materials IRRADIATION TESt at the MIT Research Reactor | Lin-wen Hu | | + | | {{ : |
| - | | RESEARCH REACTOR POWER CONTROL SYSTEM DESIGN BY MATLAB/ | + | | {{ : |
| - | | SIMULATION OF POWER MANEUVERING USING COUPLED ANALYSIS OF KINETICS AND THERMAL-HYDRAULICS IN A RESEARCH REACTOR | H. KIM, S.K. PARK, C. PARK, S.J. KIM, T.W. NOH | | + | | {{ : |
| - | | CABRI EXPERIMENTAL REACTOR: EXPERIMENTAL REASSESSMENT OF CABRI CORE POWER AND MEASUREMENT UNCERTAINTIES | F. JEURY*, L. PANTERA, Y. GARNIER | | + | | {{ : |
| - | | Computational Analysis of Nuclear Safety Parameters of 3 MW TRIGA Mark-II Research Reactor Based on Evaluated Nuclear Data Libraries JENDL-3.3 and ENDF/ | + | | {{ : |
| - | | OPAL REACTOR: CALCULATION/ | + | | {{ : |
| - | | NEUTRON NOISE MEASUREMENT IN THE CROCUS REACTOR | V. Roland, G. Perret, G. Girardin, P. Frajtag, A. Pautz | | + | | {{ : |
| - | | VALIDATION OF REACTOR PHYSICS-THERMAL HYDRAULICS COUPLED CALCULATION IN WATER-COOLED RESEARCH REACTORS WITH LAMINAR FLOW REGIMES | K.A. JORDAN, D. SCHUBRING, G. GIRARDIN, A. PAUTZ | | + | | {{ : |
| - | | CONTRIBUTION OF CAD AND PLM FOR RESEARCH REACTOR DESIGN AND CONSTRUCTION | X. BONNETAIN, P. GUILLOU, E. DRIDI, C. PASCAL | | + | | {{ : |
| - | | ESTIMATION OF ADJOINT-WEIGHTED KINETICS PARAMETERS IN MONTE CARLO WIELANDT CALCULATIONS | SUNG HOON CHOI, HYUNG JIN SHIM | | + | | {{ : |
| - | | THE EOLE CRITICAL FACILITY IN SUPPORT TO EXPERIMENTAL REACTOR CORE PHYSICS VALIDATION: THE EXAMPLE OF AMMON EXPERIMENTAL PROGRAM FOR JHR START-UP VALIDATION | P. BLAISE, A. GRUEL, J. DI SALVO, H. AMHARRAK, A. ROCHE, JF. LEDOUX, JM. GIRARD, C. VAGLIO-GAUDARD, | + | | {{ : |
| - | | AN INNOVATIVE IN-CORE SODIUM LOOP FOR IRRADIATION OF MULTIPLE SAMPLES AT HIGH TEMPERATURES: | + | | {{ : |
| - | | Utilizing the burnup capability in MCNPX to perform depletion analysis of an MNSR fuel | Emmanuel Boafo | | + | | {{ : |
| - | | FUEL PERFORMANCE EVALUATION OF MINI-PLATE IRRADIATION TEST OF U-7MO DISPERSION FUEL FOR KJRR | Y.W. TAHK, J.Y. OH, B.H. LEE, H.J. KIM, J.S. YIM, H.T. CHAE, C.G. SEO, J.M. PARK | | + | | {{ : |
| - | | PRELIMINARY STUDY OF PLATE FUEL CONCEPT BASED ON COATED PARTICLE FOR RESEARCH REACTOR | HIDAYATULLAH RULLY and YONGHEE KIM | | + | | {{ : |
| - | | Impact Analysis for Fuel Assemblies in Spent Fuel Storage Rack | J. H. Oh, J. S. Ryu | | + | | {{ : |
| - | | Assessment of Structural Integrity of the Pool Door for Research Reactor | Jinbok Choi | | + | | {{ : |
| - | | A CONCEPTUAL STUDY FOR THE DEVELOPMENT OF A LOW POWER RESEARCH REACTOR | C. PARK, H.S.KIM, J.H.PARK, H.T.CHAE, B.C.LEE | | + | | {{ : |
| + | | {{ : | ||
| + | </ | ||
proceedings/2013_igorr15.1703748468.txt.gz · Last modified: 2023/12/28 08:27 by Joerg Pulz