本文關(guān)鍵詞：測(cè)繪工程實(shí)驗(yàn)室建設(shè)模式的探索，由筆耕文化傳播整理發(fā)布。

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自然地理學(xué)和測(cè)繪學(xué)

surveying laboratory

     Study on the Construction Mode of Surveying Laboratory

     測(cè)繪工程實(shí)驗(yàn)室建設(shè)模式的探索

短句來(lái)源

     It analyzes the factors that affect the teaching effect according to several years' of teaching practice of surveying. And it also puts forward some countermeasures in view of how to select the teaching contents and models, how to determine the teaching depth, breadth and the length for teaching practice as well as the opening of the surveying laboratory.

     根據(jù)幾年的測(cè)量學(xué)教學(xué)實(shí)踐 ,分析影響教學(xué)效果的因素 ,如教學(xué)內(nèi)容的取舍、教學(xué)的深度與廣度、教學(xué)模式的選擇、實(shí)驗(yàn)室的開(kāi)放以及實(shí)習(xí)時(shí)間的長(zhǎng)短等 ,提出了有針對(duì)性的改革措施

短句來(lái)源

     In this paper,the author puts forward some ideas to improve the quality of experimental teaching in surveying,such as strengthening the hardware and system construction of the surveying laboratory,setting up a stable teaching training base in the campus and a moving production training base out of the campus.

     結(jié)合筆者幾年來(lái)參與實(shí)驗(yàn)室及實(shí)習(xí)基地建設(shè)的經(jīng)驗(yàn),提出了加強(qiáng)實(shí)驗(yàn)室的硬件建設(shè)和制度建設(shè),建立固定的校內(nèi)教學(xué)實(shí)習(xí)基地與動(dòng)態(tài)的校外生產(chǎn)實(shí)習(xí)基地結(jié)合的方法,以提高測(cè)量學(xué)實(shí)踐教學(xué)質(zhì)量。

短句來(lái)源

     Laboratory;

     實(shí)驗(yàn);

短句來(lái)源

     Construction of Surveying Basic Laboratory

     測(cè)量基礎(chǔ)實(shí)驗(yàn)室建設(shè)的實(shí)施

短句來(lái)源

     Study on the Construction Mode of Surveying Laboratory

     測(cè)繪工程實(shí)驗(yàn)室建設(shè)模式的探索

短句來(lái)源

     Laboratory Animala

     實(shí)驗(yàn)動(dòng)物

短句來(lái)源

     SURVEYING IN ANTARCTICA

     南極測(cè)繪

短句來(lái)源

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>=Radiation Protection is an integral component of the development of atomic energy related programme in India including nuclear fuel cycle facilities. The radiation protection standards are basically derived from ICRP recommendations and IAEA’s Basic Safety Standards. A well structured regulatory organization exists in the country. The radiation protection standards in nuclear fuel cycle facilities and NPPs are implemented through the Health Physics Unit (HPU) and Environmental Survey Laboratories (ESL)...

>=Radiation Protection is an integral component of the development of atomic energy related programme in India including nuclear fuel cycle facilities. The radiation protection standards are basically derived from ICRP recommendations and IAEA’s Basic Safety Standards. A well structured regulatory organization exists in the country. The radiation protection standards in nuclear fuel cycle facilities and NPPs are implemented through the Health Physics Unit (HPU) and Environmental Survey Laboratories (ESL) established at these plants. The HPUs and ESLs are independent of the plant management and they report to Health Safety & Environment Group, BARC. Adequate personnel monitoring programme has been established at all the sites. Training of personnel is an important aspect of the radiation protection programme. With the importance given to the implementation of protection standards generally the dose received by occupational workers is well below the regulatory limits. Cases of exposure above the limits are negligible. Dose to public from radioactive effluents are only a small fraction of the limit.

Radiation Protection is an integral component of the development of atomic energy related programme in India including nuclear fuel cycle facilities. The radiation protection standards are basically derived from ICRP recommendations and IAEA’s Basic Safety Standards. A well structured regulatory organization exists in the country. The radiation protection standards in nuclear fuel cycle facilities and NPPs are implemented through the Health Physics Unit (HPU) and Environmental Survey Laboratories (ESL) esta...

Radiation Protection is an integral component of the development of atomic energy related programme in India including nuclear fuel cycle facilities. The radiation protection standards are basically derived from ICRP recommendations and IAEA’s Basic Safety Standards. A well structured regulatory organization exists in the country. The radiation protection standards in nuclear fuel cycle facilities and NPPs are implemented through the Health Physics Unit (HPU) and Environmental Survey Laboratories (ESL) established at these plants. The HPUs and ESLs are independent of the plant management and they report to Health Safety & Environment Group, BARC. Adequate personnel monitoring programme has been established at all the sites. Training of personnel is an important aspect of the radiation protection programme. With the importance given to the implementation of protection standards generally the dose received by occupational workers is well below the regulatory limits. Cases of exposure above the limits are negligible. Dose to public from radioactive effluents are only a small fraction of the limit.

>=In India, Environmental Survey Laboratories set up at nuclear power plant sites are responsible for monitoring the environment for radioactivity and assessment of population dose. Accurate and precise measurement of low levels of 137Cs and 90Sr in environmental matrices is essential to assess and differentiate the contribution due to global fallout and nuclear plant discharges during routine monitoring. The limitations of conventionally used is techniques of pre-concentration of 137Cs using ammonium...

>=In India, Environmental Survey Laboratories set up at nuclear power plant sites are responsible for monitoring the environment for radioactivity and assessment of population dose. Accurate and precise measurement of low levels of 137Cs and 90Sr in environmental matrices is essential to assess and differentiate the contribution due to global fallout and nuclear plant discharges during routine monitoring. The limitations of conventionally used is techniques of pre-concentration of 137Cs using ammonium phospho molybdate (AMP), cation exchange separation and beta counting of separated cesium were discussed. An inconsistent recovery for 90Sr in large volume of seawater with routine methods was observed. The paper presents radio-analytical and instrumental techniques developed for the accurate determination of fall out level 137Cs and 90Sr in coastal seawater and also discusses the limitations encountered in the commonly followed radiochemical separation techniques.

In India, Environmental Survey Laboratories set up at nuclear power plant sites are responsible for monitoring the environment for radioactivity and assessment of population dose. Accurate and precise measurement of low levels of 137Cs and 90Sr in environmental matrices is essential to assess and differentiate the contribution due to global fallout and nuclear plant discharges during routine monitoring. The limitations of conventionally used is techniques of pre-concentration of 137Cs using ammonium phospho...

In India, Environmental Survey Laboratories set up at nuclear power plant sites are responsible for monitoring the environment for radioactivity and assessment of population dose. Accurate and precise measurement of low levels of 137Cs and 90Sr in environmental matrices is essential to assess and differentiate the contribution due to global fallout and nuclear plant discharges during routine monitoring. The limitations of conventionally used is techniques of pre-concentration of 137Cs using ammonium phospho molybdate (AMP), cation exchange separation and beta counting of separated cesium were discussed. An inconsistent recovery for 90Sr in large volume of seawater with routine methods was observed. The paper presents radio-analytical and instrumental techniques developed for the accurate determination of fall out level 137Cs and 90Sr in coastal seawater and also discusses the limitations encountered in the commonly followed radiochemical separation techniques.

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  本文關(guān)鍵詞：測(cè)繪工程實(shí)驗(yàn)室建設(shè)模式的探索，，由筆耕文化傳播整理發(fā)布。