Swelling behavior of U-Pu-Zr fuel

被引：0
|
作者：
机构：
[1] Hofman, Gerard L.
[2] Pahl, R.G.
[3] Lahm, C.E.
[4] Porter, D.L.
来源：
Hofman, Gerard L. | 1600年 / 21 A期
关键词：
Composition Effects - Swelling;
D O I：
暂无
中图分类号：
学科分类号：
摘要：
(Edited Abstract)
引用
收藏
相关论文
共 50 条
  • [21] CONSTITUENT MIGRATION MODEL FOR U-PU-ZR METALLIC FAST-REACTOR FUEL
    ISHIDA, M
    OGATA, T
    KINOSHITA, M
    NUCLEAR TECHNOLOGY, 1993, 104 (01) : 37 - 51
  • [22] Interdiffusion in U-Pu-Zr and U-Zr-Ti solid solutions
    Alexeev, OA
    Shmakov, AA
    Smirnov, EA
    PLUTONIUM FUTURES-THE SCIENCE, 2000, 532 : 135 - 137
  • [23] Mass spectrometric studies on U-Pu-Zr alloy
    Manikandan, P.
    Trinadh, V. V.
    Bera, Suranjan
    Narasimhan, T. S. Lakshmi
    Ananthasivan, K.
    Joseph, M.
    JOURNAL OF NUCLEAR MATERIALS, 2018, 507 : 339 - 346
  • [24] Interdiffusion in the bcc phase of the U-Pu-Zr system
    Alekseev, OA
    Smirnov, EA
    Shmakov, AA
    ATOMIC ENERGY, 1998, 84 (04) : 260 - 266
  • [25] Interdiffusion in the BCC phase of an U-Pu-Zr system
    Alekseev, O.A.
    Smirnov, E.A.
    Shmakov, A.A.
    1998, Ministry of the Russian Federation on Atomic Energy, Moscow, Russian Federation (84):
  • [26] Thermochemically-informed mass transport model for interdiffusion of U and Zr in irradiated U-Pu-Zr fuel with fission products
    Poschmann, Max
    Piro, Markus H. A.
    Besmann, Theodore M.
    Clarno, Kevin T.
    Simunovic, Srdjan
    JOURNAL OF NUCLEAR MATERIALS, 2021, 554
  • [27] Evaluation of long chain monoamide extractants for the reprocessing of U-Pu-Zr metallic fuel solution
    Prathibha, T.
    Selvan, B. Robert
    Venkatesan, K. A.
    JOURNAL OF RADIOANALYTICAL AND NUCLEAR CHEMISTRY, 2019, 320 (03) : 765 - 773
  • [28] FISSION PRODUCT RELEASE FROM AN ENCAPSULATED U-PU-ZR TERNARY ALLOY FUEL ELEMENT
    SMITH, RR
    EBERSOLE, ER
    FRYER, RM
    HENAULT, PB
    TRANSACTIONS OF THE AMERICAN NUCLEAR SOCIETY, 1969, 12 (01): : 180 - &
  • [29] Fuel-Cladding Chemical Interaction in U-Pu-Zr Metallic Fuels: A Critical Review
    Matthews, Christopher
    Unal, Cetin
    Galloway, Jack
    Keiser, Dennis D., Jr.
    Hayes, Steven L.
    NUCLEAR TECHNOLOGY, 2017, 198 (03) : 231 - 259
  • [30] Modeling constituent redistribution in U-Pu-Zr metallic fuel using the advanced fuel performance code BISON
    Galloway, J.
    Unal, C.
    Carlson, N.
    Porter, D.
    Hayes, S.
    NUCLEAR ENGINEERING AND DESIGN, 2015, 286 : 1 - 17
12345