Works in Nuclear Technology, 2010, Vol 170, Issue 1

Results: 24

DEVELOPMENT OF THE FISSION PRODUCT RELEASE ANALYSIS CODE COPA-FPREL.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 231, doi. 10.13182/NT10-A9461

By:

YOUNG MIN KIM;
MOON SUNG CHO

Publication type:

Article

THE DEFOR-S EXPERIMENTAL STUDY OF DEBRIS FORMATION WITH CORIUM SIMULANT MATERIALS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 219, doi. 10.13182/NT10-A9460

By:

KUDINOV, PAVEL;
KARBOJIAN, ARAM;
MA, WEIMIN;
DINH, TRUC-NAM

Publication type:

Article

DEVELOPMENT OF AN AUTOMATED TESTING SYSTEM FOR VERIFICATION AND VALIDATION OF NUCLEAR DATA AND SIMULATION CODE.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 80, doi. 10.13182/NT10-A9447

By:

TRIPLETT, BRIAN S.;
ANGHAIE, SAMIM;
WHITE, MORGAN C.

Publication type:

Article

INTERACTION BETWEEN MOLTEN CORIUM UO2+x-ZrO2-FeOy AND VVER VESSEL STEEL.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 210, doi. 10.13182/NT10-A9459

By:

BECHTA, S. V.;
GRANOVSKY, V. S.;
KHABENSKY, V. B.;
KRUSHINOV, E. V.;
VITOL, S. A.;
SULATSKY, A. A.;
GUSAROV, V. V.;
ALMIASHEV, V. I.;
LOPUKH, D. B.;
BOTTOMLEY, D.;
FISCHER, M.;
PILUSO, P.;
MIASSOEDOV, A.;
TROMM, W.;
ALTSTADT, E.;
FICHOT, F.;
KYMALAINEN, O.

Publication type:

Article

MINOR ACTINIDE-BEARING OXIDE FUEL CORE DESIGN STUDY FOR THE JSFR.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 170, doi. 10.13182/NT10-A9455

By:

NAGANUMA, MASAYUKI;
OGAWA, TAKASHI;
OHKI, SHIGEO;
MIZUNO, TOMOYASU;
KOTAKE, SHOJI

Publication type:

Article

COMPARISON OF THE HIGH-TEMPERATURE STEAM OXIDATION KINETICS OF ADVANCED CLADDING MATERIALS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 272, doi. 10.13182/NT10-A9464

By:

GROSSE, M.

Publication type:

Article

CORROSION STUDIES OF CANDIDATE MATERIALS FOR EUROPEAN HPLWR.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 261, doi. 10.13182/NT10-A9463

By:

PENTTILÄ, SAMI;
TOIVONEN, AKI;
HEIKINHEIMO, LIISA;
NOVOTNY, RADEK

Publication type:

Article

ANALYSIS AND JUSTIFICATION OF MAAP4.0.7 FOR PRA LEVEL 1 MISSION SUCCESS CRITERIA.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 244, doi. 10.13182/NT10-A9462

By:

BUTLER, JENNIFER S.;
KAPITZ, DARVIN;
MARTIN, ROBERT P.;
SEIFAEE, FARROKH;
SUNDARAM, RAMU K.

Publication type:

Article

EUROPEAN EXPERIMENTS ON 2-D MOLTEN CORE CONCRETE INTERACTION: HECLA AND VULCANO.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 189, doi. 10.13182/NT10-A9457

By:

JOURNEAU, CHRISTOPHE;
BONNET, JEAN MICHEL;
BOCCACCIO, ERIC;
PILUSO, PASCAL;
MONERRIS, JOSE;
BRETON, MICHEL;
FRITZ, GERALD;
SEVÓN, TUOMO;
PANKAKOSKI, PEKKA H.;
HOLMSTRÖM, STEFAN;
VIRTA, JOUKO

Publication type:

Article

TRANSIENT CONDUCTION HEAT TRANSFER MODELING IN CONCRETE FOR THE SIMULATION OF LONG-TERM PHASE OF MOLTEN CORE-CONCRETE INTERACTION.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 201, doi. 10.13182/NT10-A9458

By:

TOURNIAIRE, B.;
SPINDLER, B.;
GUILLAUMÉ, M.

Publication type:

Article

OPTIMAL GEOMETRIC CONFIGURATION FOR A NATURAL CIRCULATION LOOP.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 114, doi. 10.13182/NT10-A9450

By:

JIN HO SONG

Publication type:

Article

DEVELOPMENT OF PASSIVE SHUTDOWN SYSTEM FOR SFR.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 181, doi. 10.13182/NT10-A9456

By:

NAKANISHI, SHIGEYUKI;
HOSOYA, TAKUSABURO;
KUBO, SHIGENOBU;
KOTAKE, SHOJI;
TAKAMATSU, MISAO;
AOYAMA, TAKAFUMI;
IKARIMOTO, IWAO;
KATO, JUNGO;
SHIMAKAWA, YOSHIO;
HARADA, KIYOSHI

Publication type:

Article

AN INTEGRAL EFFECT TEST ON THE REFLOOD PERIOD OF A LARGE-BREAK LOCA FOR THE APR1400 USING ATLAS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 100, doi. 10.13182/NT10-A9449

By:

HYUN SIK PARK;
KI YONG CHOI;
SEOK CHO;
KYOUNG HO KANG;
NAM HYUN CHOI;
DONG JIN EUH;
YEON SIK KIM;
WON PIL BAEK

Publication type:

Article

HEAT TRANSFER IN INTERMEDIATE HEAT EXCHANGER UNDER LOW FLOW RATE CONDITIONS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 90, doi. 10.13182/NT10-A9448

By:

MOCHIZUKI, HIROYASU

Publication type:

Article

TECHNOLOGICAL FEASIBILITY OF TWO-LOOP COOLING SYSTEM IN JSFR.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 159, doi. 10.13182/NT09-6

By:

YAMANO, HIDEMASA;
KUBO, SHIGENOBU;
KURISAKA, KEN-ICHI;
SHIMAKAWA, YOSHIO;
SAGO, HIROMI

Publication type:

Article

SYSTEM DESIGN AND ANALYSIS OF A 900-MW(thermal) LEAD-COOLED FAST REACTOR.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 148, doi. 10.13182/NT10-A9453

By:

SANG JI KIM;
YONGHEE KIM;
SERGI HONG;
CHUNG HO CHO;
JAE-HYUK EOH;
JONG BUM KIM;
MYUNG HWAN WI;
KWI SEOK HA;
EUI KWANG KIM

Publication type:

Article

DEVELOPMENT OF ADVANCED LOOP-TYPE FAST REACTOR IN JAPAN.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 133, doi. 10.13182/NT10-7

By:

KOTAKE, SHOJI;
SAKAMOTO, YOSHIHIKO;
KUBO, SHIGENOBU;
UTO, NARIAKI;
KAMISHIMA, YOSHIO;
AOTO, KAZUMI;
TODA, MIKIO;
MIHARA, TAKATSUGU

Publication type:

Article

LARGE BREAK LOSS-OF-COOLANT ACCIDENT ANALYSIS OF VVER-1000 REACTOR USING CATHARE CODE.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 123, doi. 10.13182/NT10-A9451

By:

SABOTINOV, LUBEN;
SRIVASTAVA, ABHISHEK

Publication type:

Article

THE ENHANCEMENTS AND TESTING FOR THE MCNPX 2.6.0 DEPLETION CAPABILITY.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 68, doi. 10.13182/NT10-2

By:

FENSIN, MICHAEL L.;
HENDRICKS, JOHN S.;
ANGHAIE, SAMIM

Publication type:

Article

PARAMETRIC SENSITIVITY STUDY ON THE REFLOODING MODELS OF THE MARS CODE BASED ON 6 x 6 ROD BUNDLE TEST RESULTS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 54, doi. 10.13182/NT10-A9445

By:

KI-YONG CHOI;
SEOK CHO;
HYOUNG-KYU CHO;
CHUL-HWA SONG

Publication type:

Article

THERMAL-FLUID CHARACTERIZATIONS OF ZnO AND SiC NANOFLUIDS FOR ADVANCED NUCLEAR POWER PLANTS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 16, doi. 10.13182/NT10-A9442

By:

BANG, IN CHEOL;
KIM, JI HYUN

Publication type:

Article

AN ASSESSMENT OF LARGE-EDDY SIMULATION TOWARD THERMAL FATIGUE PREDICTION.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 2, doi. 10.13182/NT10-A9441

By:

KUCZAJ, A. K.;
KOMEN, E. M. J.

Publication type:

Article

SUMMARY FOR THREE DIFFERENT VALIDATION CASES OF COOLANT FLOW IN SUPERCRITICAL WATER TEST SECTIONS WITH THE CFD CODE ANSYS CFX 11.0.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 40, doi. 10.13182/NT10-A9444

By:

KISS, ATTILA;
ASZÓDI, ATTILA

Publication type:

Article

SPECIAL ISSUE ON THE 2008 INTERNATIONAL CONGRESS ON ADVANCES IN NUCLEAR POWER PLANTS.

Published in:

Nuclear Technology, 2010, v. 170, n. 1, p. 1, doi. 10.13182/NT10-A9440

By:

ANGHAIE, SAMIM

Publication type:

Article