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REFERENCE LINKING PLATFORM OF KOREA S&T JOURNALS
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Nuclear Engineering and Technology
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Journal DOI :
Korean Nuclear Society
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Volume & Issues
Volume 22, Issue 4 - Dec 1990
Volume 22, Issue 2 - Jun 1990
Volume 22, Issue 1 - Mar 1990
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The Analytical Radioactive Waste Repository Source Term REPS Model
Kim, Chang-Lak ; Cho, Chan-Hee ; Park, Kwang-Sub ; Kim, Jinwung ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 315~325
The analytical repository source term (REPS) computer code is developed for the safety assessment of radioactive waste geologic repository. For reliable prediction of the leach rates for various radionuclides, degradation of concrete structures, corrosion rate of waste container, degree of corrosion on the container surface, and the characteristics of radionuclides are considered in this REPS code. For the validation of the radionuclide leach rates predicted by the REPS model, the calculated leach rates of Cs-137, Sr-85, and Co-60 are compared with two reported leaching test results. Cesium and strontium leach congruently, and the leaching test results of these species can be reproduced by the congruent leaching model included in the REPS model. In case of cobalt, the solid diffusion model is in good agreement with the leaching test results.
Incorporation of Droplet Breakup Model at Spacer Grid into RELAP5/ MOD2
Park, Jong-Ho ; Lee, Sang-Yong ; Kim, Si-Hwan ; Chang, Soon-Heung ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 326~336
Recent experiments show the existence of spacer grid improves the heat removal from the fuel rods during the reflood phase of LOCA. The local heat transfer within and downstream of the grid is increased due to the earlier quenching than rod surface, shattering of the entrained droplets into smaller ones which can be more easily evaporated and enhanced turbulent effect. Therefore, the consideration of these phenomena is necessary for the DFFB regime which prevails above the water level during the reflood. In this paper, droplet breakup model at spacer grid has been developed and incorporated into RELAP5/MOD2. Verification calculations are carried out for FEBA tests which examine the thermalhydraulic performance of grid spacer during reflood.
A Study on the Recovery of Radiation Hardening of PWR Pessure Vessel Steel Using Michrohardness and Positron Annihilation
Garl, Seong-Je ; Yoon, Young-Ku ; Park, Soon-Pil ; Park, Yong-Ki ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 337~350
A post-irradiation annealing study was conducted with use of reactor pressure vessel(RPV) steel A533B Cl.1 base metal irradiated to a dose of 4.84
at about 38
. Microhardness and positron annihilation (PA) methods were used to obtain better understanding of the recovery of radiation hardening. Isochronal anneal experiments indicated that two recovery processes occur during annealing of irradiated specimens. The first recovery process occurs in the temperature range of 280-3O5
, Michrohardness and positron annihilation (PA) methods were used to obtain better understanding of the recovery of radiation hardening. Isochronal anneal experiments indicated that two recovery processes occur during annealing of irradiated specimens. The first recovery process occurrs in the temperature range of 280-305
. The variations of Ip, Iw and R parameters indicated that the formation of vacancy clusters by vacancy agglomeration and the annihilation of monovacancies are the first recovery process. The second recovery process occurs in the range of 405-49
and positron annihilation parameters measured indicated that the dissolution of carbon atoms decorated around vacancy-type defects and possible precipitates, and the annihilation of monovacancies give rise to the second recovery process. It was further indicated that radiation anneal hardening (RAH) in the range of 305-405
between the temperature ranges for the two processes occurs due to the formation of carbon-decorated vacancy clusters and precipitates. The activation energies, orders of reaction and other characteristics of recovery processes were determined by the Meechan-Brinkman method. The activation energy for the first recovery process was determined as 1.76 eV and that for the second recovery process as 2.00eV. These values are lower than those obtained by other workers. This difference may be attributed to the lower copper content of the RPV steel used in the present study. The order of reaction for the first recovery process was determined as 1.78, while that for the second recovery process as 1.67 Non-integer orders of reaction for recovery processes seem to be attributed to the fact that several mechanisms for the first order and the second order of reaction are compounded in one process. This result also supports for the above conclusions from measurements of PA parameters.
Fission-product Burnup Chain Model for Research Reactor Application
Kim, Jung-Do ; Gil, Choong-Sup ; Lee, Jong-Tai ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 351~358
A new fission-product burnup chain model was developed for use in research reactor analysis capable of predicting the burnup-dependent reactivity with high precision over a wide range of burnup. The new model consists of 63 nuclides treated explicitly and one fissile-independent pseudo-element. The effective absorption cross sections for the pseudo-element and the pseudo-element yield of actinide nuclides were evaluated in the this report. The model is capable of predicting the high burnup behavior of low-enriched uranium-fueled research reactors.
A Comparison of Low-Dimensional Reactor Kinetics Analysis Methods with Modified Borresen's Coarse-Mesh Method
Kim, Chang-Hyo ; Lee, Gyu-Bok ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 359~370
This study concerns with comparing low-dimensional reactor kinetics methods with a three-dimensional kinetics method to be used for safety analysis of light water reactors in order to suggest means of preparing input parameters required for low-dimensional methods. For this purpose a one-dimensional finite difference two-group diffusion theory code ODTRAN and a third-order Hermit polynomial-based point kinetics code POTRAN are developed and used to obtain low-dimensional solutions to the LRA-BWR kinetics benchmark problem. The results are compared with a three-dimensional modified Borresen's coarse-mesh solution of the kinetics problem by CMSNACK code. Through this comparison some simple but practical means of preparing input parameters of low-dimensional kinetics analysis methods are suggested.
Generalized Nyquist Criterion for the Stability of Xenon Oscillation
Park, You-Cho ; Park, Goon-Cherl ; Chung, Chang-Hyun ; Park, Chong-Kyun ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 371~379
The Xenon spatial oscillation may give rise to operational difficulties in a nuclear power plant. In this study, in order to investigate the Xenon instability for a PWR, the frequency-domain technique is adopted by using Generalized Nyquist Criterion, which is more general and suitable for the multi-input/multi-output system. Also linearized modal fluxes are obtained by a modal expansion. This model has been implemented to test the axial Xenon stability of YGN-1 unit against the changes in plant operating parameters ; power level, control rod position, and core average burnup. The results show that the increase of power level and the deeper insertion of control rod have the destabilizing effect, and that the burnup progress makes the core less stable. Also the results show that the overestimation due to modal interaction was found not to be significant.
Design Features and Operating Characteristics of the MM-22 Microtron for Radiotherapy
Bak, Joo-Shik ; Lee, Dong-Hun ;
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 380~388
The MM-22 medical microtron at Korea Cancer Center Hospital is now operational for high energy electron and photon therapy, This microtron is designed to produce 5.3-22.5 MeV electron beams and deliver these to the treatment head through beam transport system with an intensity and stability suitable for cancer treatment. The availability of high quality radiation modalities from the MM-22 shows new possibilities in the treatment of deep seated tumours. Principle of operation, system structures and operating characteristics of the MM-22 are described in this paper.
Technical and Economic Evaluations of CANDU Advanced Fuel Bundle Designs
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 389~409
As a principal design of advanced CANDU fuel bundle, CANDU-KF39, CANDU-KF40 and CANDU-KF43 fuel bundles were proposed and evaluated with respect to the operating conditions of the CANDU-6 reactor of Wolsung Unit-1. From the results, the advanced fuel bundles show to be improved economical and technical benefits compared with the current 37-element bundle. Especially, it was appeared that the KF-39 fuel bundle has more benefits of the safety, technical and economical aspects of Wolsung Unit-1 rather than those of the KF-40 and KF-43 fuel bundles.
Method for Measuring Prompt Fission Neutron Energy Spectrum by Means of Threshold Activation Detectors
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 410~415
Prompt fission neutron energy spectrum as a function of energies of neutron inducing fission has been calculated en the basis of the Madland-Nix(MN) model. The resultant spectra have been weighted to excitation functions of
S(n, p) and
In(n, n') threshold reactions in order to get the average cross sections and then spectral indices which are defined as the average cross section ratio for two selective threshold reactions among the above three. It is appeared that spectral indices together with the neutron spectra are varying with energies of neutron inducing fission. This may indicate that the prompt fission neutron energy spectrum can be determined by measuring experimentally the spectral index.
방사성 폐기물 관리에 있어 감용처리기술의 중요성
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 416~422
TMI-2 원자로의 로심재 핫셀시험결과 검토분석
Nuclear Engineering and Technology, volume 22, issue 4, 1990, Pages 423~435