Analysis of a loss of feedwater transient with safety/relief valve stuck open in Chin Shan nuclear power station |
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Annual report |
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Application of gas chromatography and gamma spectrometry on fission gas measurement |
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ASMCOD, a postprocessor for piping system structure analysis program to perform ASME class 1, 2, and 3 stress checks |
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Assessment of critical heat flux correlations for high steam quality condition |
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The blocking of coded files in preparing a magnetic tape |
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Capital cost estimates of CANDU-600 by the CONCEPT-5 code |
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Chung-hua min kuo shih fa yeh chin chi shu yen tʻao hui (2nd : 1982 : Taipei, Taiwan). Chung-hua min kuo ti 2 chieh shih fa yeh chin chi shu yen tʻao hui chuan chi, 1982: |
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The conversion of MCA data from punched tape to disk file |
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Criticality calculation of tight lattice core utilizing Monte Carlo code MORSE-CG |
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Design, fabrication, and calibration of orifice flow meters for operation with water at pressures up to 2500 psia |
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Determination of the neutron energy and neutron fluxes for a laboratory-fabricated neutron generator |
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Determinations of boron and chloride in highly radioactive sample solution : presented at the International Conference on Methods and Applications of Radioanalytical Chemistry, April 5-10, 1987, Kona, Hawaii |
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The enlarged production of thorium oxide microsphere by gel-supported precipitation technique |
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Experience and utilization of the Taiwan research reactor : presented at the 3rd Pacific Basin Conference, February 16-18, 1981, in Acapulco, Mexico |
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An experimental investigation of water post-CHF boiling in forced vertical flow |
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Fast breeder reactor core design considerations |
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A FORTRAN code for solving mixed integer linear programming problems |
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FRAPCON-2 predictions of the fuel centerline temperatures in IFA-431 and IFA-432 assemblies |
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Graphic display of structural model using SAP6/7 |
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A guide to computer code MORSE-CG general purpose Monte Carlo multigroup neutron and gamma-ray transport code with combinatorial geometry |
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He yan ji kan. |
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Ho yen chi kʻan, Oct. 10, 1991: |
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Investigation of 9B and 9Be levels in kinematically complete 9Be (p, pn) 8Be experiment |
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An investigation of delayed time between neutron power and thermal power in TRR by noise analysis method |
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Je shih tsu. Kao fang she shih ... 1977. |
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A low cost multichannel pulse waveform recorder |
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LWR spent fuel radioactive decay predictions by ORIGEN2 and PC data base application |
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Main steam line break accident analysis for Maanshan units 1&2 using RETRAN-02/MOD2 code |
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The manipulation and application of the vitamin-C 171-neutron, 36-gamma ray group cross section library |
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Mathematical subroutine library for the CDC CYBER-73 computer at INER |
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The non-linear system limit cycle analysis for feedwater control system of BWR |
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Nuclear energy research on advanced LWRs in ROC : presented at ANS International Executive Conference, Taipei, ROC, December 7-8, 1983, as the appendix of the paper "Research on advanced LWRs in INER, ROC" (INER-0524) |
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Nuclear power plant evacuation planning : an expert system approach |
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Optical analysis of Littrow-McCubbin monochromator |
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PICTURE : a FORTRAN subroutine package for drawing three-dimensional representation of a two-dimensional array |
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Prediction of incipient boiling of low pressure water in a horizontal forced convection channel |
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Production of carrier-free phosphorus-32 |
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Pulsed high-power microwaves from a virtual-cathode reflex triode |
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PWR outside core radiation source evaluation using EMERS code package |
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Qualification of the steam generator thermal-hydraulic code THERMIT-UTSG. |
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Solvent extraction in hydrometallurgical applications : presented at the Symposium on Transport Phenomena and Its Applications, Taipei, June 26, 1978 |
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Solving of inverse z-transfer function by recurrent permutation method |
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Status report of the research activities in using the experimental facilities at Taiwan Research Reactor |
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Status report on nuclear fuel development program and related research activities at the Institute of Nuclear Energy Research |
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Steam generator tube rupture analyses for Maanshan nuclear power plant |
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Studies on the adsorption behaviors of protactinium-233 on silica gel and unfired vycor glass in nitric acid medium |
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Study of at-power neutron noise based on multigroup diffusion theory |
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The study of chromosome aberration yield in human lymphocytes as an indicator of radiation dose |
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A study of creep mechanisms--with emphasis on uranium-oxide and zircaloy |
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A study on shelf life extension of papayas irradiated by 60Co gamma-rays |
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Time-of-flight measurement of the neutron total cross section of HB-40 from 0.008 eV to 1.5 eV with a fast chopper |
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TRR spent fuel model for the ORIGEN2 code |
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Uranium adsorption with composite titanium-iron hydrous oxide microspheres : presented at the International Meeting on Recovery of Uranium from Seawater 1983, Tokyo, Japan, October 17-19, 1983 |
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Uranium utilization improvement in LWR : paper presented at the CNS/ANS Taiwan Section Topical Meeting on Nuclear Fuel Cycle Technology, Taipei, Taiwan, ROC, September 29-30, 1982 |
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A user's manual for ANISCAT : a code to evaluate the reflected dose off the primary shield into reactor cavity |
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Ying yong xun you she ji fang fa she ji luo xuan xing ya su dan huang |
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Zhonghua min guo di 2 jie shi fa ye jin ji shu yan tao hui zhuan ji = 1982 Hydrometallurgical Symposium |
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應用尋優設計方法設計螺旋形壓縮彈簧 |
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放射性同位素生産與應用 = Radioisotope production and application. |
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核硏季刊. |
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行政院原子能委員會核能研究所 = Institute of Nuclear Energy Research, Atomic Energy Council, Executive Yuan, Republic of China. |
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