SE189026C1 - - Google Patents

Info

Publication number
SE189026C1
SE189026C1 SE189026DA SE189026C1 SE 189026 C1 SE189026 C1 SE 189026C1 SE 189026D A SE189026D A SE 189026DA SE 189026 C1 SE189026 C1 SE 189026C1
Authority
SE
Sweden
Prior art keywords
alloy
silver
indium
cadmium
neutron
Prior art date
Application number
Other languages
English (en)
Swedish (sv)
Publication date
Publication of SE189026C1 publication Critical patent/SE189026C1/sv

Links

Landscapes

  • Monitoring And Testing Of Nuclear Reactors (AREA)
SE189026D SE189026C1 (esLanguage)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE189026T

Publications (1)

Publication Number Publication Date
SE189026C1 true SE189026C1 (esLanguage) 1963-01-01

Family

ID=41975903

Family Applications (1)

Application Number Title Priority Date Filing Date
SE189026D SE189026C1 (esLanguage)

Country Status (1)

Country Link
SE (1) SE189026C1 (esLanguage)

Similar Documents

Publication Publication Date Title
Steinbrück et al. Oxidation of advanced zirconium cladding alloys in steam at temperatures in the range of 600–1200° C
Yagnik et al. Effect of alloying elements, cold work, and hydrogen on the irradiation-induced growth behavior of zirconium alloy variants
US3074871A (en) Alloy composition for neutronic reactor control rods
CN1128235C (zh) 用作燃料棒包覆层的锆合金
Chiswik et al. Advances in the physical metallurgy of uranium and its alloys
KR20020062742A (ko) 물과 수증기에 의한 내식성과 수소화에 대한 내성이우수한 지르코늄 합금 및 당해 합금의 가공열 변태방법
CN103290261A (zh) 锆合金及使用它制备核燃料包壳的方法
Stahl Fuels for research and test reactors, status review: July 1982
SE189026C1 (esLanguage)
Bandriyana et al. Effect of copper addition on the high temperature oxidation of zirconium alloy ZrNbMoGe for advanced reactor fuel cladding material
Kruger Preparation and some properties of arc-cast plutonium monocarbide
JPH0660364B2 (ja) ビスマスを含有する耐食性ジルコニウム合金
Volkov et al. Use of burnable poisons in nuclear reactors
US3782924A (en) Fine-grained zirconium-base material
US8043448B2 (en) Non-heat treated zirconium alloy fuel cladding and a method of manufacturing the same
US9305667B1 (en) Nuclear fuel alloys or mixtures and method of making thereof
US3663218A (en) Burnable poison for nuclear reactor
US2929706A (en) Delta phase plutonium alloys
US3188202A (en) Aluminum-plutonium alloys
US3219541A (en) Method of preventing carburization of fuel element cladding metals by uranium carbide fuels
EP1634974A1 (en) Process of manufacturing nuclear reactor components in zirconium alloy
Song Effect of yttrium additions on the elevated-temperature tensile properties and hardness of an advanced iron-nickel-chromium LMFBR cladding and duct alloy
Sears et al. DEVELOPMENT AND IRRADIATION TESTING OF A]-U3Si2 FUEL AT CHALK RIVER LABORATORIES
Wullaert et al. AN EVALUATION OF UC--PuC FOR SODIUM-COOLED FAST REACTORS.
Horak et al. The Effects of Irradiation on some Binary Alloys of Thorium-Plutonium and Zirconium-Plutonium