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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
> Journal Vol & Issue
Nuclear Engineering and Technology
Journal Basic Information
Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 31, Issue 6 - Dec 1999
Volume 31, Issue 5 - Oct 1999
Volume 31, Issue 4 - Aug 1999
Volume 31, Issue 3 - Jun 1999
Volume 31, Issue 2 - Apr 1999
Volume 31, Issue 1 - Feb 1999
Selecting the target year
Nuclear Design Methodology of Fission Moly Target for Research Reactor
Cho, Dong-Keun ; Kim, Myung-Hyun ; Sohn, Dong-Seong ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 365~374
A nuclear design of fission moly production targets for a research reactor, HANARO was peformed. It was found that the use of MCNP-4A, ORIGEN-2 code was reliable for the analysis of production characteristics of
Mo in a target fuel at an irradiation holes. A parametric study was done for the optimization of target location, target dimension, target shape and fuel materials. It was shown that a fuel thickness was the most sensitive parameters and electro-deposited target gave the highest 99Mo yield ratio. A pellet target with vibro-compaction powder, however, showed the largest production capacity and better engineering feasibility even with less yield ratio. Ten kinds of optimized target design for both LEU and HEU satisfied all the given design constraints. The most favorable design was the HEU ring-shaped electro-deposited target, considered the safety limit, production yield, chemical process easiness, yield ratio, and amount of radioactive waste.
Demonstration of EPRI CHECWORKS Code to Predict FAC Wear of Secondary System Pipings of a Nuclear Power Plant
Lee, Sung-Ho ; Seong Jegarl ; Chung, Han-Sub ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 375~384
The credibility of CHECWORKS FAC model analysis was evaluated for plant application in a model plant chosen for demonstration. The operation condition at each pipe component was defined before the wear rate analysis by plant data base, water chemistry analysis, and network flow analysis. The predicted wear was compared with the measured wear for 57 sample components selected from 43 susceptible line groups analysed. The inspected 57 locations represent components of highest predicted wear in each line group. Both absolute value and relative ranking comparisons indicated reasonable correlations between the predicted and the measured values. Four components showed much higher measured wear rates than the predicted ones in the feed water train from main feed water pump discharge to steam generator, probably due to high hydrazine concentration operation the effect of which had not been incorporated into the CHECWORKS model. The measured wear was higher than the predicted one consistently for components with least susceptibility to FAC. It is believed that the conservatism maintained during UT data analysis dominated the measurement accuracy. A great deal of enhancement is anticipated over the current plant pipe management program when a comprehensive plant pipe management program is implemented based on the model analysis.
Morphological Anomaly of Primordial Follicle in
Kim, Jin-Kyu ; Lee, Chang-Joo ; Lee, Young-Keun ; Song, Kang-Won ; Park, Ho-Hyun ; Yoon, Yong-Dal ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 385~390
Ovarian follicles are faced with one of two fates, atresia or development. Up to 99% of follicles become degenerated rather than ovulated in female life span. Thus, atresia occurs at all stages of follicle development in mammalian ovaries. In the present experiment, the effect of
-radiation on primordial follicles was morphologically analyzed in a mouse ovary. Thirty-seven percent of the primordial follicles in the non-irradiated control mice ovaries were abnormal. At day 8 post irradiation, most of primordial follicles became atretic. They lost their integrity of architecture in the follicular shape. Then, all the oocytes disappeared from the follicles. And only 3 to 4 granulosa cells lay down onto the basement membrane. Disappearance of granulosa cells or oocytes resulted from the radiation-induced apoptotic process. It is definitely clear that
-radiation induces rapid apoptotic degeneration of the primordial follicles. The morphological degeneration induced by radiation in the primordial follicles can be used as an experimental model to draw out a deeper insight for radioprotectant researches.
Conceptual Core Design of 1300MWe Reactor for Soluble Boron Free Operation Using a New Fuel Concept
Kim, Soon-Young ; Kim, Jong-Kyung ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 391~400
A conceptual core design of the 1,300MWe KNGR (Korean Next Generation Reactor) without using soluble boron for reactivity control was developed to determine whether it is technically feasible to implement SBF (Soluble Boron Free) operation. Based on the borated KNGR core design, the fuel assembly and control rod configuration were modified for extensive use of burnable poison rods and control rods. A new fuel rod, in which Pu-238 had been substituted for a small amount of U-238 in fuel composition, was introduced to assist the reactivity control by burnable poison rods. Since Pu-238 has a considerably large thermal neutron capture cross section, the new fuel assembly showed good reactivity suppression capability throughout the entire cycle turnup, especially at BOC (Beginning of Cycle). Moreover, relatively uniform control of power distribution was possible since the new fuel assemblies were loaded throughout the core. In this study, core excess reactivity was limited to 2.0 %
for the minimal use of control rods. The analysis results of the SBF KNGR core showed that axial power distribution control can be achieved by using the simplest zoning scheme of the fuel assembly Furthermore, the sufficient shutdown margin and the stability against axial xenon oscillations were secured in this SBF core. It is, therefore, concluded that a SBF operation is technically feasible for a large sized LWR (Light Water Reactor).
in the Fast Critical Assembly BFS and Validation of a
Computation Code, BETA-K
Kim, Taek-Kyum ; Kim, Young-Il ; Kim, Young-Jin ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 401~407
We have performed two experiments in the fast critical assembly BFS to measure the effective delayed neutron fraction
values and compared the results to validate the
computation code, BETA-K. Measurements of
were carried out in a metallic plutonium core and a metallic uranium core with Cf
source pseudo-reactivity method. Fission integrals and correction factors, which were used to obtain the experimental
values, were calculated by using the LMR core design computation code system of KAERI. BETA-K has been developed consistently with the hexagonal Nodal Expansion Method (NEM) and it used delayed neutron data of ENDF/B-VI. By comparing the computed
values with the measured ones, we found that the results from BETA-K agreed with the experimental values within the experimental error bound.ror bound.
Investigating the Fluence Reduction Option for Reactor Pressure Vessel Lifetime Extension
Kim, Jong-Kyung ; Shin, Chang-Ho ; Seo, Bo-Kyun ; Kim, Myung-Hyun ; Kim, Dong-Kyu ; Lee, Goung-Jin ; Oh, Su-Jin ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 408~422
To reduce the fast neutron fluence which deteriorates the RPV integrity, additional shields were assumed to be installed at the outer core structures of the Kori Unit 1 reactor, and its reduction effects were examined. Full scope Monte Carlo simulation with MCNP4A code was made to estimate the fast neutron fluence at the RPV. An optimized design option was found from various choices in geometry and material for shield structure. It was expected that magnitude of fast neutron fluence would be reduced by 39% at the circumferential weld of the RPV, resulting in extension of plant lifetime by 4.6 EFPYs based on the criterion of PTS requirement It was investigated that the nuclear characteristics and thermal hydraulic factors at the internal core were only negligibly influenced by the installation of additional shield structure.
Monitoring of Rotational Movements of Two Piston Rings in a Cylinder Using Radioisotopes
Jung, Sunghee ; Jin, Joonha ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 423~431
A radiotracer technique has been developed to monitor the rotational movement of two piston rings in one cylinder during engine operation. The rings were labeled with two different kinds of radioisotopes, i.e.
Ir, for identification of the top ring from the second ring. The radiotracers were implanted in a small hole bored on the inner side of each piston ring. The rings were installed in a single cylinder hydrogen engine and three Nal scintillation detectors were mounted around the engine block to measure the gamma radiation. The angle of ring-gap orientation was determined from the radiation counts measured with the three detectors during engine operation. Two windows (upper window for
Co and lower window for
Ir) were set on each ratemeter to count radiation from the two isotopes separately. Procedure to convert the radiation counts to the position of the ring gap was established. With the software programmed with MS-Visualbasic, radiation counts were compared with the reference responses that were measured at angular intervals of 10
for each piston ring in advance of the experiment. The result was used for the evaluation of the relationship between the orientation of ring-gaps and oil consumption. It was found that an increase in the oil consumption rate of a specific operation condition was closely related to the relative phase angle of the two piston rings.
Two-Dimensional Nuclide Transport Around a HLW Repository
Lee, Youn-Myoung ; Kang, Chul-Hyung ; Hwang, Yong-Soo ; Chun, Kwan-Sik ;
Nuclear Engineering and Technology, volume 31, issue 4, 1999, Pages 432~443
Using a two-dimensional numerical model, nuclide transport in the buffer between the canister and adjacent rock in a high-level radioactive waste repository is dealt with. Calculations are made for a typical case with a three-member decay chain,
Ra. The solution method used here is based on a physically exact formulation by a control volume method directly integrating the governing equation over each control volume.