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📐 ASME STP-NU-018-2009 is a nuclear-industry technical report prepared by Tai Asayama and Yukio Tachibana of the Japan Atomic Energy Agency (JAEA) and issued on May 21, 2009, with 166 pages. Sponsored by the DOE and ASME ST-LLC, the report studies two representative elevated-temperature structural materials with a common framework: Grade 91 (modified 9Cr-1Mo) steel, widely used in fast-reactor and supercritical steam generator components, and Hastelloy XR, a nickel-based alloy developed for the intermediate heat exchanger (IHX) of high-temperature gas-cooled reactors (HTGR/HTTR). The report has two goals — to systematically collect, screen, and organize the historical creep, fatigue, and creep-fatigue data of both materials into a database usable for Code revision, and to quantitatively compare the prediction accuracy of the ASME-NH, Japanese DDS, and French RCC-MR creep-fatigue evaluation procedures.
The report is organized in two main parts. Part I (Grade 91) first consolidates a list of data sources for creep, fatigue, and creep-fatigue testing of modified 9Cr-1Mo steel at 400 °C and above, then details the ASME-NH, DDS, and RCC-MR procedures and compares how each treats strain range, initial hold-time stress, relaxation, and creep damage. Evaluations are performed both “without safety margins” and “according to Code procedures.” Environmental effects (air oxidation under tensile and compressive holds), thermal aging, and the conceptual relationship between the time-fraction and ductility-exhaustion methods are then examined. Part II (Hastelloy XR) covers the alloy’s development background and data, the creep-fatigue criteria of the Japanese HTGR high-temperature structural design guideline, an inelastic analysis of the HTTR IHX as an application example, and the R&D items needed for Generation IV and very-high-temperature reactors (VHTR).
The report divides Grade 91 data into three dimensions: creep, fatigue, and creep-fatigue properties. Creep data come from long-term databases such as ORNL and Japan’s NIMS, covering temperatures of 400 °C and above; fatigue data consist mainly of strain-controlled continuous-cycling tests; creep-fatigue data include both tensile-hold and compressive-hold tests. Three “points to be addressed” are highlighted: first, the effect of compressive holds cannot simply be ignored, since in air they can substantially shorten life through the interaction of creep damage and oxidation; second, the prediction bias of the time-fraction rule for Grade 91 under long holds; and third, the systematic quantification of prediction differences among the procedures on the same data.
| Data Category | Primary Sources | Typical Test Conditions | Issues Addressed |
|---|---|---|---|
| Creep | ORNL, NIMS (Japan), European databases | 400–650 °C, stresses covering long-term rupture | Scatter of mid-temperature strength; extrapolation reliability |
| Fatigue | Strain-controlled continuous cycling | 500–600 °C, graded strain ranges | Acceleration of crack initiation by air oxidation |
| Creep-fatigue | Tensile/compressive hold tests | Hold times from 0.1 to 10 h | Damage contribution of compressive holds; accuracy of time-fraction rule |
| Influence factors | Environment/aging control tests | Air vs. vacuum; retesting after prior aging | Effects of thermal aging on cyclic behavior and creep ductility |
The report tabulates the differences among ASME-NH, DDS, and RCC-MR. For strain range, ASME-NH relies mainly on elastic analysis with elastoplastic correction, while DDS and RCC-MR lean on inelastic analysis; for the initial hold-time stress, ASME-NH starts from the elastic solution corrected for relaxation, RCC-MR from the inelastic solution; for creep damage, ASME-NH and DDS use the time-fraction rule (or a derivative), while RCC-MR uses ductility exhaustion. The report then predicts lives for the same Grade 91 creep-fatigue data with all three procedures without safety margins and compares with measured life: the time-fraction rule systematically overpredicts life (non-conservatively) in the long-hold region, while ductility exhaustion tends to underpredict (conservatively); the two converge in the high-stress, short-life region.
| Evaluation Step | ASME-NH | Japanese DDS | French RCC-MR |
|---|---|---|---|
| Strain range determination | Elastic analysis + elastoplastic correction | Primarily inelastic analysis | Inelastic analysis or simplified correction |
| Initial hold-time stress | Elastic calculation + relaxation correction | Inelastic calculation | Inelastic relaxation curve |
| Stress relaxation estimate | Simplified relaxation relation | Based on measured relaxation | Integral relaxation with creep constitutive law |
| Creep damage accumulation | Time-fraction rule | Based on time-fraction rule | Ductility exhaustion |
| Tendency under long holds | Overpredicts life (non-conservative) | Between the two extremes | Underpredicts life (conservative) |
Hastelloy XR is a nickel-based alloy modified from standard Hastelloy X specifically for high-temperature gas-cooled reactors; its composition is adjusted to improve corrosion resistance in high-temperature helium and long-term microstructural stability, and it is the designated material of the intermediate heat exchanger (IHX) of Japan’s High Temperature Engineering Test Reactor (HTTR). Part II of the report summarizes how the Japanese HTGR structural design guideline identified failure modes, developed design limits and rules, and characterized Hastelloy XR, and then presents an inelastic analysis of the HTTR IHX to examine creep-fatigue damage accumulation under design conditions. These results provide a direct engineering precedent for rating comparable high-temperature nickel-based alloy components in Generation IV and VHTR systems.
Based on both parts, the report puts forward improvement proposals. Short-term items include correcting the treatment of creep ductility in creep damage evaluation, introducing environment corrections that reflect material behavior, and adding benchmark tests with compressive holds in air; long-term items include developing a hybrid damage model unifying time-fraction and ductility-exhaustion methods, building an inelastic constitutive-equation framework for Gen IV and VHTR, and systematically studying the effect of helium environments on the creep-fatigue life of nickel-based alloys. The report also recommends that ASME-NH borrow the “identify failure modes first, then develop design limits” methodology used in the Japanese HTGR design guideline.