Development on crack growth and crack initiation test units for stress corrosion cracking examinations in high-temperature water environments under neutron irradiation, 1 (Contract research)

Izumo, Hironobu; Chimi, Yasuhiro; Ishida, Takuya; Kawamata, Kazuo; Inoue, Shuichi; Ide, Hiroshi; Saito, Takashi; Ise, Hideo; Miwa, Yukio; Ugachi, Hirokazu; et al.

JAEA-Technology 2009-011, 31 Pages, 2009/04

JAEA-Technology-2009-011.pdf:4.38MB

Regarding Irradiation Assisted Stress Corrosion Cracking (IASCC) for austenitic stainless steel of the light water reactor (LWR), a lot of data that concerns the post irradiation evaluation (PIE) is acquired. However, IASCC occurs in LWR condition. Therefore, it is necessary to confirm adequacy of the PIE data comparing the experiment data under the simulated LWR condition. Bigger specimen is needed to acquire the effective data for the destruction dynamics in the study of stress corrosion cracking under neutron irradiation condition. Therefore, development of a new crack growth unit which can load to bigger is necessary to the neutron irradiation test. As a result, a prospect was provided in the unit that could load to specimen by changing load mechanism to the lever type from the linear type. And also, in the development of crack propagation unit, some technical issues were extracted from the discussion of the unit structure adopting the LVDT (Linear Variable Differential Transformer).

JAERI-JNC joint research report; A Study on degradation of structural materials used under the irradiation environment in nuclear reactors

Ueno, Fumiyoshi*; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Takaya, Shigeru; Hoshiya, Taiji; Tsukada, Takashi*; Aoto, Kazumi; Ishii, Toshimitsu*; Omi, Masao*; et al.

JNC TY9400 2005-013, 150 Pages, 2005/09

JNC-TY9400-2005-013.pdf:37.33MB

None

JNC-JAERI united research report; A Study on degradation of structural materials under irradiation environment in nuclear reactors (Joint research)

Hoshiya, Taiji; Ueno, Fumiyoshi*; Takaya, Shigeru; Nagae, Yuji; Nemoto, Yoshiyuki*; Miwa, Yukio*; Aoto, Kazumi; Tsukada, Takashi*; Abe, Yasuhiro; Nakamura, Yasuo; et al.

JNC TY9400 2004-026, 53 Pages, 2004/10

JNC-TY9400-2004-026.pdf:22.07MB

Japan Nuclear Cycle Development Institute (JNC) and Japan Atomic Energy Research Institute (JAERI) have started a JNC-JAERI united research program cooperatively in 2003, which has been aimed for efficient progress and synergistic effect on the research activities of both Institutes in order to lead the facing task of unification between JNC and JAERI. This study has been chosen one of the united research themes, and the purpose of it is to clarify damage mechanism of structural materials under irradiation, and then to develop the methods for damage evaluation and detection in earlier stage of progressing process of damage. In fiscal year 2003, magnetic flux density distribution (JNC) and micro-corrosion (JAERI) measurement apparatus were newly developed and equipped in Hot Facilities in two Institutes, respectively. These apparatus were designed and produced in consideration of radiation resistance and remote-controlled operation to equip in hot cells. We will start the study on neutron irradiation damage by employing the two apparatus as the next step.

Damage evaluation techniques for FBR and LWR structural materials based on magnetic and corrosion properties along grain boundaries

Hoshiya, Taiji*; Takaya, Shigeru*; Ueno, Fumiyoshi; Nemoto, Yoshiyuki; Nagae, Yuji*; Miwa, Yukio; Abe, Yasuhiro*; Omi, Masao; Tsukada, Takashi; Aoto, Kazumi*

Transactions of the Materials Research Society of Japan, 29(4), p.1687 - 1690, 2004/06

JAERI and JNC have begun the cooperative research of evaluation techniques of structural material degradation in FBR and LWR, which based on magnetic and corrosion properties along grain boundaries. Magnetic method has been proposed as the one of the non-destructive detection techniques on the early stage of creep-damage before crack initiation for aged structural materials of FBRs. The effects of applied stress on natural magnetization were investigated on paramagnetic stainless steels having creep-damages. On the other hand, corrosion properties and magneto-optical characteristics of ion-irradiated stainless steels in the vicinity of grain boundaries were estimated by AFM and Kerr effect microscope, respectively. These degradations were induced by changes in characteristics in the vicinity of grain boundaries. It is found that the initial level of progressing process of damage can detect changes in magnetic and corrosion properties along grain boundaries of aged and degraded nuclear plants structural materials.

Irradiation test plan of fuels and materials for light water reactors in JMTR

Chimi, Yasuhiro; Nishiyama, Yutaka; Ise, Hideo; Nakamura, Takehiko; Ishitsuka, Etsuo; Tsukada, Takashi

no journal, , 

Japan Atomic Energy Agency (JAEA) has a plan of refurbishment of Japan Materials Testing Reactor (JMTR) and reoperation from FY 2011 in order to contribute to development and safe operation of light water reactors (LWRs). Installation of fuels and materials irradiation facilities in JMTR is now in progress in parallel with the refurbishment of JMTR. In the present report, we give an outline of fuels and materials irradiation tests by using JMTR, especially neutron irradiation test program on materials for reactor pressure vessel steels and core shrouds for solving issues on plant aging, and current status of installation of the test facilities in JMTR.

Studies on the effective dose for public calculated by air dose rate

Endo, Yuya; Yamaguchi, Katsuhiko*; Takase, Tsugiko*; Uezu, Yasuhiro; Tsukada, Hirofumi*

no journal, , 

After the Fukushima Dai-ichi Nuclear Power Station accident, the Ministry of the Environment decided that the additional annual dose in a high exposure situation (less than 20 mSv/y) reduced to 1 mSv/y or less. The additional annual dose is calculated by ambient dose equivalent. However, the relationship among air kerma, ambient dose equivalent and effective dose seems to be identically by many people. In addition, conversion coefficients from air kerma and ambient dose equivalent to effective dose have been considered to change as time proceeds because the half-lives of Cs and Cs are different. Therefore, agricultural land in an evacuation zone was selected to evaluate relationship among them. Furthermore, the actual environment such as soil will be simulated by using a Monte Carlo radiation transport code PHITS. Finally, the relationship will be verified by comparing the results calculated by PHITS to ones obtained from actual environmental monitoring.