Considerations of Irradiation-Induced Transient Creep in Fuel Particle Modeling.

• Gregory K. MILLER

  Idaho National Engineering Laboratory, Lockheed Idaho Technologies Company

抄録

An analytical assessment is made of the potential effects of irradiation-induced transient creep on the behavior of the TRISO-coated fuel particles of the New Production Modular High Temperature Gas-Cooled Reactor (NP-MHTGR). An analytical solution is presented for the three-layer particles, which includes transient creep in addition to steady-state creep behavior. The solution allows for evaluating the effects that transient creep has on individual particle stresses and for determining failure probabilities for particle batches using the Monte Carlo approach. Because experimental data needed to determine parameters for a transient component in a creep model for the pyrocarbons is not available, a range of possible parameter values were considered in the assessments. It was shown that transient creep measurably affects particle stresses early in the irradiation life of the particle. At that time, the hoop stress in the primary load bearing layer of the particle is in compression and the particle is not vulnerable to pressure vessel failure. Later in irradiation, the effects of transient creep were typically shown to be less significant. Thus, transient creep had less than an order of magnitude effect on batch failure probabilities for prototypical NP-MHTGR fuel particles and was much less significant than steady-state creep. Whether the presence of transient creep increased or decreased the particle failure probability was dependent on the specific values used for the transient creep material properties.

収録刊行物

• Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌）

  Ｊｏｕｒｎａｌ　ｏｆ　Ｎｕｃｌｅａｒ　Ｓｃｉｅｎｃｅ　ａｎｄ　Ｔｅｃｈｎｏｌｏｇｙ（日本原子力学会英文論文誌） 32 (10), 989-1000, 1995

  一般社団法人 日本原子力学会

キーワード

• NP-MHTGR reactor
• pyrocarbon
• silicon carbide
• TRISO-coated fuel particles
• transient creep
• steady state creep
• swelling
• Monte Carlo method
• FUEL
• ABAQUS
• failure probability
• viscoelastic
• fast neutron fluence
• Weibull distribution
• Gauss distribution

詳細情報

• CRID: 1390001204095316096
• NII論文ID: 10002073334
• NII書誌ID: AA00703720
• DOI: 10.3327/jnst.32.989
• COI: 1:CAS:528:DyaK2MXpsValsro%3D
• ISSN: 18811248
• ISSN: 00223131
• 本文言語コード: en
• データソース種別:
  • JaLC
  • Crossref
  • CiNii Articles
• 抄録ライセンスフラグ: 使用不可