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
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 basically necessary for the safety analysis of the capsule and capsule detail 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 obtained fast neutrons (E>1.0MeV) by using the SANDII code are located within about a 20% error range of the theoretical 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 DPA (Displacement Per Atom) and activation of the irradiated specimens are also evaluated by using the SPECTOR and ORIGEN2 codes, respectively, at HANARO.
Keywords :
Monte Carlo methods; neutron effects; neutron spectra; nuclear materials safeguards; ANSYS code; GENGTC code; HANARO material irradiation capsule; High flux Advanced Neutron Application Reactor; MCNP code; ORIGEN2 code; SANDII code; SPECTOR code; irradiation temperature; irradiation test parameter; neutron fluence; neutron irradiation damage; neutron spectrum; nuclear material; safety analysis; Activation analysis; Atomic measurements; Fuels; Heating; Inductors; Materials testing; Neutrons; Safety; System testing; Temperature; DPA and activation; HANARO capsule; irradiation temperature; neutron fluence;
Conference_Titel :
Advancements in Nuclear Instrumentation Measurement Methods and their Applications (ANIMMA), 2009 First International Conference on
Conference_Location :
Marseille
Print_ISBN :
978-1-4244-5207-1
Electronic_ISBN :
978-1-4244-5208-8
DOI :
10.1109/ANIMMA.2009.5503823