ICONE11-36136 Program of in-pile IASCC testing under the simulated actual plant condition : Development of Technique for In-pile IASCC Initiation Test in JMTR
スポンサーリンク
概要
- 論文の詳細を見る
Irradiation assisted stress corrosion cracking (IASCC) is caused by the synergistic effects of neutron irradiation, stress and corrosion by high temperature water. It is, therefore, essential to perform in-pile SCC tests, which are material tests under the conditions simulating those of actual LWR operation, in order to clarify the precise mechanism of the phenomenon, though mainly out-of-pile SCC tests for irradiated materials have been carried out in this research field. There are, however, many difficulties to perform in-pile SCC tests. Performing in-pile SCC tests, essential key techniques must be developed. Hence as a part of development of the key techniques for in-pile SCC tests, we have embarked on development of the test technique which enables us to obtain the information concerning the effect of such parameters as applied stress level, water chemistry, irradiation conditions, etc. on the crack initiation behavior. Although it is difficult to detect the crack initiation in in-pile SCC tests, the crack initiation can be evaluated by the detection of specimen rupture if the cross section area of the specimen is small enough. Therefore, we adopted the uniaxial constant loading (UCL) test with small tensile specimens. This paper will describe the current status of the development of several techniques for in-pile SCC initiation tests in JMTR and the results of the performance tests of the designed testing unit using the out-of-pile loop facility.
- 一般社団法人日本機械学会の論文
著者
-
TAKIGUCHI Hideki
Japan Atomic Power Co.
-
KAJI Yoshiyuki
Japan Atomic Energy Research Institute
-
TSUJI Hirokazu
Japan Atomic Energy Research Institute
-
TSUKADA Takashi
Japan Atomic Energy Agency
-
Takiguchi Hideki
Japan Atomic Power Company
-
Matsui Yoshinori
Japan Atomic Energy Agency
-
Komori Yoshihiro
Japan Atomic Energy Agency
-
Kaji Yoshiyuki
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
-
UGACHI Hirokazu
Japan Atomic Energy Agency
-
NAGATA Nobuaki
Japan Atomic Power Company
-
DOZAKI Koji
Japan Atomic Power Company
-
Tsuji Hirokazu
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
-
Tsukada Takashi
Department Of Nuclear Energy System Japan Atomic Energy Research Institute
-
Kaji Yoshiyuki
Japan Atomic Energy Agency
関連論文
- Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (IV) : Comparison of Wall Thinning Rates Calculated with the Coupled Model of Static Electrochemical Analy
- Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures
- SB-02-2(075) Multiaxial Creep Behavior of Nickel-Base Heat-Resistant Alloys Hastelloy XR and Ni-Cr-W Superalloy at Elevated Temperatures(Materials Performance in Nuclear Application 2)
- Effects of Hydrogen Peroxide on Corrosion of Stainless Steel, (V) Characterization of Oxide Film with Multilateral Surface Analyses
- Evaluation of Effectiveness of Hydrogen Water Chemistry for Different Types of Boiling Water Reactors
- ICONE11-36145 SSRT FACILITY FOR IN-SITU OBSERVATION IN HIGH TEMPERATURE WATER OF IRRADIATED MATERIALS
- Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (III) : Effect of Chemical Cleaning on Long Term Integrity of Steam Generator Tube after Chemical Cleaning Process
- Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (II) : Effect of Chemical Cleaning on Integrity of SG Tubing under Accelerated IGSCC Conditions
- Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (I) Outline of the Investigation and Cleaning Effectiveness
- Development of a Filler Metal for Weldments of a Ni-Cr-W Superalloy with High Creep Strength(Special Issue on Creep and Fatigue at Elevated Temperatures)
- SB-02-1(064) Development of a filler metal for weldments of a Ni-Cr-W superalloy with high creep strength(Materials Performance in Nuclear Application 2)
- In-Core SCC Growth Behavior of Type 304 Stainless Steel in BWR Simulated High-Temperature Water at JMTR
- ICONE11-36136 Program of in-pile IASCC testing under the simulated actual plant condition : Development of Technique for In-pile IASCC Initiation Test in JMTR
- ICONE11-36119 PROGRAM OF IN-PILE IASCC TESTING UNDER THE SIMULATED ACTUAL PLANT CONDITION : Development of technique for in-pile IASCC growth test in JMTR
- ICONE11-36106 Program of in-pile IASCC testing under the simulated actual plant condition : Thermohydraulic design study of saturated temperature capsule for IASCC irradiation test
- Creep Properties of Base Metal and Welded Joint of Hastelloy XR Produced for High-Temperature Engineering Test Reactor in Simulated Primary Coolant Helium
- ICONE11-36324 Program of in-pile IASCC testing under the simulated actual plant condition : Overview
- ICONE11-36111 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36107 Stress corrosion cracking susceptibility of thermally sensitized type 304 stainless steels doped with various levels of carbon and silicon
- ICONE11-36093 AFM EVALUATION FOR CORROSION BEHAVIOR OF ION IRRADIATED STAINLESS STEEL
- Development of Analytical Method and Study about Microstructure of Oxide Films on Stainless Steel
- Status of JAERI Material Performance Database(JMPD)and Analysis of Irradiation Assisted Stress Corrosion Cracking(IASCC)Data
- SB-03-3(074) Inelastic Constitutive Equation in Alloy800H(Materials Performance in Nuclear Application 3)
- Applicability of Chemical Cleaning Process to Steam Generator Secondary Side, (IV) : Comprehensive Applicability Evaluation of Chemical Cleaning and Its Effect on Integrity of Other Structural Materials Other than Steam Generator Tubes
- Creep Properties under Varying Stress/Temperature Conditions on Nickel-Base Heat-Resistant Alloy Hastelloy XR