DocumentCode :
1352551
Title :
Measurement and Evaluation of the Irradiation Test Parameters for a Specimen in a HANARO Material Irradiation Capsule
Author :
Choo, K.N. ; Kim, B.G. ; Cho, M.S. ; Kim, Y.K. ; Ha, J.J.
Author_Institution :
Korea Atomic Energy Res. Inst., Daejeon, South Korea
Volume :
57
Issue :
5
fYear :
2010
Firstpage :
2642
Lastpage :
2646
Abstract :
A material capsule system has been developed for irradiation tests of nuclear materials in the core region of the high-flux advanced neutron application reactor (HANARO) and has been actively utilized for the various material irradiation tests requested by numerous users. For an irradiation test in the reactor, nuclear characteristics and irradiation temperature of the capsule parts are essential for the safety analysis of the capsule and for the detailed capsule design. The irradiation temperature and neutron fluence of the specimens are key parameters required by a user to analyze any neutron irradiation damage effects. Based on a basic design of a capsule, the reactivity effect, neutron flux/fluence, and gamma heating of specimens are calculated by the MCNP code. To compare the calculated neutron fluence of the specimens, thermal and fast fluence monitors (F/Ms) are installed in a capsule. After an irradiation, the F/Ms are dismantled and analyzed to obtain a neutron spectrum. The experimental fast neutron fluences (E > 1.0 MeV) derived by using the SAND II code were found to lie within about 20% of the predicted values calculated by the MCNP code. The irradiation temperature of the specimens is analyzed preliminary by using the GENGTC or ANSYS codes based on the basic design of a capsule and gamma heating. During an irradiation test, the temperatures of the specimens in a capsule are measured and monitored by thermocouples. The displacement per atom (DPA) and activation of the irradiated specimens are also evaluated by using the SPECTER and ORIGEN2 codes, respectively, at HANARO.
Keywords :
fission reactor core control; fission reactor design; fission reactor materials; fission reactor safety; fission research reactors; neutron flux; ANSYS code; GENGTC code; HANARO material irradiation capsule; MCNP code; SAND II code; capsule design; core region; displacement per atom; gamma heating; high-flux advanced neutron application reactor; irradiation temperature; irradiation test parameters; material capsule system; material irradiation tests; neutron fluence; neutron flux; neutron irradiation damage effects; neutron spectrum; nuclear materials; reactivity effect; safety analysis; thermocouples; Heating; Inductors; Materials; Neutrons; Radiation effects; Temperature measurement; Displacement per atom (DPA) and activation; High-flux advanced neutron application reactor (HANARO) capsule; irradiation temperature; neutron fluence;
fLanguage :
English
Journal_Title :
Nuclear Science, IEEE Transactions on
Publisher :
ieee
ISSN :
0018-9499
Type :
jour
DOI :
10.1109/TNS.2010.2059044
Filename :
5603698
Link To Document :
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