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Evaluation report on CCTF core-II-reflood test C2-5 (Run 63) : Effect of decay heat level on PWR reflood phenomena
1991
Iguchi Tadashi
2409
0
Evaluation report on CCTF CORE-II reflood test C2-15 (RUN 75) : Investigation of flechtset coupling test results
1992
Okubuo Isutomu, Iguchi Tadashi, Akimoto Hajime, Murao Yoshio
2352
0
Evaluation report on CCTF core - II reflood test C2-I (Run 55) : Effect of pressure on reflood phenomena
1991
Iguchi Tadashi
1957
0
Étude paramétrique sur le cycle en pile du combustible des coeurs de réacteurs à eau légère pressurisée sous l'aspect physique et économique : Thèse
1977
Guillet Jean-Luc
2542
0
Untersuchungen zur thermo-hydraulischen Stabilität von Dampferzeugern für Druckwasserreaktoren : Vortrag und Compact präsentiert auf der Deutschen Reaktortagung 1975 in Nürnberg
1975
Jütte Klaus, Bruneder Heinrich, Nevyjel Alexander
1139
0
Comparison of facility characteristics between SCTF core-I and core-II
1990
Adachi Hiromichi, Iwamura Takamichi, Sobajima Makoto
2711
0
Evaluation report on SCTF core-III test S3-17 : Investigation of thermo-hydrodynamic behavior during reflood phase of LOCA in a PWR with vent valves
1990
Okubo Tsutomu
2135
0
Evaluation report on CCTF Core-II reflood test C2-16 (Run 76) : Effect of asymmetric upper plenum, injection on reflood phenomena : Work done under contract with the government
1987
Iguchi Tadashi
2698
0
Evaluation report on CCTF core-II reflood test C2-8 (run 67) : Effect of system pressure
1987
Akimoto Hajime
791
0
Behavior of irradiated PWR fuel under a simulated RIA condition : Results of NSRR test MH-3
1995
Sasajima Hideo
977
0
LOLA system: a code block for nodal PWR simulation
1985
Aragones J. M.
2002
0
Implementation of implicit method into heat conduction calculation of TRAC-PF1/MOD2 code
1990
Akimoto Hajime
779
0
MARIA system: A code block for PWR fuel assembly calculations
1983
Ahnert Carolina, Aragones Jos
743
0
Assessment of TRAC-PFI/MOD1 code for core thermal hydraulic behavior during reflood with CCTF and SCTF data
1993
Akimoto Hajime
1854
0
Cross flow resistance in air-water two-phase flow in rod bundle
1987
Iwamura Takamichi, Adachi Hiromichi, Sobajima Makoto
1237
0
Laboruntersuchungen zum Verhalten radioaktiver Korrosionsprodukte im Primärkreislauf von Druckwasserreaktoren : Zusfsg. der Ergebnisse 1973 bis 1980
1982
Rommel Helmut
2263
0
Risk evaluation of local dilution transients in a pressurized water reactor : Akad. avh
1992
Jacobson Sven
1086
0
Recalculation of simulated post-scram core power decay curve for use in ROSA IV/ISTF experiments on PWR smoll-break LOCAs and transients
1990
Kumamaru Hiroshige, Tasaka Kanji
2698
0
Evaluation report on CCTF core-II reflood test C2-3 (run 61) : Investigation of initial down comer water accumulation velocity effects
1987
Okubo Tsutomu
1508
0
Pipe rupture test results: 4-inch pipe whip test under PWR LOCA conditions (RUN N 5506, 5507, 5508, 5604)
1982
Miyazaki Noriyuki
1156
0
Modélisation thermohydraulique des écoulements et des échanges de chaleur au cours du renoyage d'un coeur de réacteur à eau pressurisée : Thèse
1977
Raymond Patrick
1342
0
Analysis of SCTF : CCTF counterpart test results
1990
Okubo Tsutomu
2067
0
Recirculation pump suction line 200% break integral test at ROSA-III with two LPCI failures, RUN 983
1984
Suzuki Mitsuhiro
1739
0
Description of code system PLES/PTS for evaluation of pressure vessel integrity during PTS events
1992
Hirano Masashi, Kohsaka Atsuo
1089
0
Evaluation report on CCTF Core-II reflood test C2-18 (run 78) : Best estimated refill/reflood upper plenum injection test : Work done under contract with the gov
1987
Iguchi Tadashi
2703
0
Digital computer code Depco-Multi for calculating the subcooled decompression in PWR Loca
1974
Namatame Ken, Kobayshi Kensuke
854
0
Evaluation report on SCTF core-III test S3-SHX : (Effect of hot leg injection on core thermal-hydraulics for PWR's with a combined injection type ECCS)
1988
Iwamura Takamichi
798
0
Alarm-P1 : A computer program for pressurized water reactor blowdown analysis
1978
Akimoto Masayuki, Araya Gumimasa, Sasaki Shinobu, Sato Kazuo
1202
0
Subcooled decompression analysis of LOFT L1-3A test data with digital computer code DEPCO-MULTI
1977
Namatame Ken, Kobayashi Kensuke, Soda Kunihisa
1095
0
Chemie der Wassers in thermischen Kraftanlagen
1984
Freier Rolf K.
2301
0
Berechnung eines Lecks im Boden eines SWR-Druckbehälters mit THYDE-B1
1988
Nathschläger Paul
2387
0
Evaluation report on CCTF core-II reflood test C2-9 (run 68) : Effect of LPCI flow rate
1987
Akimoto Hajime
1432
0
Assessment of TRAC-PFI/MOD1 code for thermal-hydraulic behavior in pressure vessel during reflood in SCTF test with a radial power distribution
1993
Ohnuki Akira, Akimoto Hajime, Murao Yoshio
1306
0
Evaluation report of SCTF core-III test S3-20 : Investigation of water break-through a. core cooling behaviors under intermittent ECC water delivery to upper plenum during reflood phase in PWRs with combined-injection type ECCS
1990
Okubo Tsutomu
2048
0
Development of SCTF cold leg injection test method for eliminating U-tube oscillation during the initial period
1990
Adachi Hiromichi, Iwamura Takamichi, Sobajima Makoto
1293
0
Analysis of PKL test K9 by Thyde-P code : (CSNI ISP N 10 a. THYDE-P sample calculation run 70)
1982
Kosugi Seiji, Sasaki Shinobu, Asahi Yoshiro
2025
0
An assessment of ²³⁸Pu and ²³⁹⁺²⁴⁰Pu in the primary cooling water of a PWR
1992
Chen Q.; Nielsen S. P.; Duniec S.
2723
0
Effects of upper plenum injection on thermo-hydrodynamic behavior under refill and reflood phases
1984
Iwamura Takamichi
1802
0
Droplets flow and heat transfer at top region of core in reflood phase
1983
Osakabe Masahiro, Ohnuki Akira, Sobajima Makoto
2344
0
Evaluation report on SCTF Core-III test S3-22 : Investigation of Water break-through a. core cooling behaviors under alternate ECC water delivery from hot legs to upper plenum during reflooding in PWRs with combined-injection type ECCS
1991
Okubo Tsutomu
2780
0
Evaluation report on SCTF core-III tests S3-14, S3-15 and S3-16 : (Effect of radial power profile shape on two-dimensional thermal-hydraulic behavior in core)
1988
Iwamura Takamichi
1219
0
Methods for optimal spatial control of pressurized water reactors : Diss.
1985
Leikkonen Ilkka
1290
0
Evaluation report on SCTF core II test S2-08 (effect of core inlet subcooling on thermal-hydraulic behavior including two-dimensional behavior in pressure vessel during reflood in PWR-LOCA)
1991
Ohnuki Akira
2695
0