scholarly journals POST-IRRADIATION EXAMINATION OF ZIRCALOY-2- AND INCOLOY-800-CLAD FUEL RODS IRRADIATED TO 7000 MWd/TU IN THE CONSUMERS BIG ROCK POINT REACTOR.

1968 ◽  
Author(s):  
V.E. Hazel
Keyword(s):  
Fuel Rods ◽  
Post Irradiation ◽  
Incoloy 800

scholarly journals POST-IRRADIATION ANALYSES OF U-MO DISPERSION FUEL RODS OF KOMO TESTS AT HANARO

2013 ◽  
Vol 45 (7) ◽  
pp. 847-858 ◽  
Author(s):  
H.J. RYU ◽  
J.M. PARK ◽  
Y.J. JEONG ◽  
K.H. LEE ◽  
Y.S. LEE ◽  
...  
Keyword(s):  
Fuel Rods ◽  
Dispersion Fuel ◽  
Post Irradiation

Test Reactor Irradiation Fuel Assembly Development in China

2017 ◽  
Author(s):  
Jie Ding ◽  
Yixiong Zheng ◽  
Yang Ding ◽  
Song Liu ◽  
Libing Zhu ◽  
...  
Keyword(s):  
Fuel Assembly ◽  
Zirconium Alloys ◽  
Reactor Irradiation ◽  
Fuel Rods ◽  
Post Irradiation ◽  
Irradiation Growth ◽  
Corrosion Creep ◽  
Test Reactor ◽  
Irradiation Performance ◽  
Test Fuel

During the development of zirconium alloys, the irradiation in the test reactor is a critical step to comparison the irradiation properties of candidate alloys, such as corrosion, creep and irradiation growth. In this paper, a small scaled fuel assembly for test reactor irradiation is designed, which meets the needs of new zirconium alloys development. The irradiation fuel assembly (IFA) can be easily disassembled, and the test fuel rods or irradiation specimen can be easily replaced, which makes it possible to do the further post-irradiation examination in the hot cell to obtain the irradiation performance data. Now the IFA has finish fabrication and the test reactor irradiation program is planned to launch in 2017.

Post-irradiation examinations of dispersion fuel rods with modified zirconium alloys claddings

2019 ◽  
pp. 206-212
Author(s):  
G. V. Kulakov ◽  
Y. V. Konovalov ◽  
A. A. Kosaurov ◽  
M. M. Peregud ◽  
V. Y. Shishin ◽  
...  
Keyword(s):  
Mechanical Properties ◽  
Corrosion Resistance ◽  
Master Alloy ◽  
Zirconium Alloys ◽  
High Strength ◽  
Fuel Rods ◽  
Dispersion Fuel ◽  
Post Irradiation ◽  
Strength And Ductility

Modified zirconium alloys E635Mand E635opt based on E635 alloy (E635 was selected as master alloy) have been developed at Bochvar Institute. Fuel rods with such claddings were manufactured at Bochvar Institute and were irradiated at MIR reactor (SC RIAR, Dimitrovgrad). The results from the PIE performed at RIAR are presented. Such features of claddings as microstructures, corrosion resistance (width and structure of oxide), hydrogen contents, distribution of hydrides, mechanical properties were examined and discussed. Modifications of the alloy E635opt and E635M showed higher resistance to corrosion and hydrogen pick-up compared to the E635 alloy, while maintaining high strength and ductility. They have confirmed their prospects for use as cladding for fuel rods with enhanced characteristics.

Study on Helium Leak Detecting for Post Irradiation Fuel Rods

2013 ◽  
Author(s):  
Liuwei Kuang ◽  
Linzhi Jiang ◽  
Liang Ren ◽  
Feiyang Yu ◽  
Chengming Guo ◽  
...  
Keyword(s):  
Mass Spectrometer ◽  
Pressure Change ◽  
Leak Rate ◽  
Leakage Detection ◽  
Leak Detector ◽  
Detection Experiment ◽  
Fuel Rods ◽  
Post Irradiation ◽  
Three Stages ◽  
Helium Leakage

In this paper, many methods on testing for post irradiation fuel rods were introduced, especially the method which used helium mass spectrometer leak detector. Helium detection device including pressure helium device, sniffer probe of helium detection device and vacuum chase leaks of helium detection device were designed. First, the device which tested and verified during the mockup experiment had been verified effectively. Then, a series of helium detection experiments were carried out for post irradiation fuel rods in hot cell. The experiments which was divided into three stages; before cutting, leak detection was carried out with sniffer probe of helium and vacuum chase leaks of helium, the background approach to leak rate, which indicated that there was no leakage or helium had been completely escape. When cutting, greater pressure change caused by helium which released from fuel rods, The result showed that there was no leakage. After cutting, in the following helium detection experiment, the background still approach to leak rate, which also indicated that there was no leakage. All the experiments indicated that helium leakage device were effective in great extent, in short, helium leakage device and method were good useful for leakage detection in hot cell, helium leak detecting for post irradiation fuel rods became true.

The Response of Testis Cells to Low Dose X-Irradiation

1981 ◽  
Vol 39 ◽  
pp. 542-543
Author(s):  
D. E. Philpott ◽  
W. Sapp ◽  
C. Williams ◽  
Joann Stevenson ◽  
S. Black
Keyword(s):  
Electron Microscopy ◽  
Stem Cell ◽  
Light Microscopy ◽  
Dose Level ◽  
Cross Sections ◽  
Low Dose ◽  
Light And Electron Microscopy ◽  
Cellular Responses ◽  
Post Irradiation ◽  
X Irradiation

The response of spermatogonial cells to X-irradiation is well documented. It has been shown that there is a radiation resistent stem cell (As) which, after irradiation, replenishes the seminiferous epithelium. Most investigations in this area have dealt with radiation dosages of 100R or more. This study was undertaken to observe cellular responses at doses less than 100R of X-irradiation utilizing a system in which the tissue can be used for light and electron microscopy.Brown B6D2F1 mice aged 16 weeks were exposed to X-irradiation (225KeV; 15mA; filter 0.35 Cu; 50-60 R/min). Four mice were irradiated at each dose level between 1 and 100 rads. Testes were removed 3 days post-irradiation, fixed, and embedded. Sections were cut at 2 microns for light microscopy. After staining, surviving spermatogonia were identified and counted in tubule cross sections. The surviving fraction of spermatogonia compared to control, S/S0, was plotted against dose to give the curve shown in Fig. 1.

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