Session: CS-10-01 Recent Developments in Japanese Codes and Standards

Paper Number: 61942

Start Time: Tuesday, July 13, 2021, 05:00 PM

61942 - Development of Leak Before Break Assessment Guidelines for Sodium Cooled Fast Reactors in Japan 

The leak before break (LBB) assessment guidelines for sodium cooled fast reactors (SFRs) is being developed in the Japan Society of Mechanical Engineers (JSME). The major purpose of the guidelines is to provide LBB assessment procedures for pipes and vessels of SFRs that retain sodium coolant. Design features of SFRs, such as high operation temperatures and low pressure coolant-systems, were taken into account. The LBB concept is used in connection to the fitness-for-service code that is also being developed for SFRs in JSME. If LBB is successfully demonstrated, volumetric examinations can be substituted by continuous leak monitoring as an in-service inspection for SFR components constituting sodium coolant boundary, such as sodium retaining pipe. The LBB assessment consists of three main paths, which are “Unstable fracture assessment”, “Leak rate assessment” and “Penetrated crack length assessment”. “Unstable fracture assessment” is conducted to determine a critical crack length, Ccr, above which unstable fracture occurs under given loading conditions. “Leak rate assessment” is carried out to determine detectable crack length, Cd, above which sodium leakage can be detected by installed leak detectors. In order to assess the Cd, a new crack opening displacement evaluation method was developed for thin walled large diameter cylindrical structures taking the geometrical feature of SFR pipes into account. “Penetrated crack length assessment” is performed to determine Cp, the crack length when a crack penetrates the wall, under given transients virtually repeated enough cycles for the crack to penetrate the wall. In order to assess the Cp, a simplified method was developed both for axial and circumferential cracks as a function of the ratio of membrane and bending stresses and fatigue crack growth characteristics. In the Cp assessment, penetrated crack length is evaluated by considering only fatigue crack growth mechanism because penetrated crack length without considering creep effects becomes longer. If Ccr is larger than both Cd and Cp, it can be concluded that LBB is demonstrated. The applicability of LBB guidelines assessment procedure was confirmed through the assessment for actual SFRs piping.

Presenting Author: Hiroki Yada Japan Atomic Energy Agency

Authors:

Hiroki Yada Japan Atomic Energy Agency
Takashi Wakai Japan Atomic Energy Agency
Takayuki Miyagawa Japan Atomic Power Company
Hideo Machida TEPCO SYSTEMS CORPORATION