• Title/Summary/Keyword: Nuclear R&D Program

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Development of R&D Policy Model for Nuclear Power Industry (원자력발전산업 기술개발정책 지원모델 개발에 관한 연구)

  • Lee, Yong-Seok;Jeong, Chang-Hyun;Kwak, Sang-Man;Kim, Do-Hyung/
    • Korean System Dynamics Review
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    • v.5 no.2
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    • pp.125-147
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    • 2004
  • System dynamics model has been developed and computer simulation has been peformed for the evaluation of R&D policy. One of the main results of the basecase scenario is as follows. After simulation of nuclear R&D resource allocation strategies, we discovered that their net benefit value was maximum at 130% nuclear R&D budget case. And after simulation of human resource management strategies and policy research program strategies, we confirmed that it is beneficial to allocate budgets in the early phase for human resources management program and research program for the policy.

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A Way to Enhance Efficiency of Nuclear Program in Korean R&D Program by Data Envelopment Analysis (자료포락분석법을 활용한 국가연구개발사업의 효율성 분석 - 원자력연구개발사업을 중심으로 -)

  • Kim, Tae-Hee;Kim, In-Ho;Ahn, Sung-Bong;Lee, Kye-Suk
    • Journal of Korea Technology Innovation Society
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    • v.12 no.1
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    • pp.70-87
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    • 2009
  • This paper studies the efficiency of public sector confronting with increasing oil price, economy crisis and energy-environment problems. In consideration that efficiency of national R&D program has been subjectively evaluated, this paper focuses objective validity by relative efficiency through a comparison among R&D programs in Korea. To implement this study, data published in national reports on R&D programs is used and analyzing method is induced by related books and theories. At the result of Data Envelopment Analysis on the collected data, this paper suggests the way to enhance the efficiency of nuclear R&D program. This study is the first on efficiency of national R&D programs applied DEA methods and is expected to contribute exploring the more efficient way of program management if more sophisticated DEA could be developed and applied.

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A Study on the Effect of Evaluators' Network on the Efficiency of Nuclear Program in Korean R&D Program (평가위원간 네트워크가 국가연구개발사업의 효율성에 미치는 영향에 관한 연구 - 원자력연구개발사업을 중심으로 -)

  • Kim, Tae-Hee
    • Journal of Korea Technology Innovation Society
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    • v.13 no.4
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    • pp.794-816
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    • 2010
  • To explore the answer on how the evaluators' network affects efficiency of National R&D Program, this paper analyzes the network of evaluators who attended the peer-review committee for National Nuclear R&D Program from 2007 to 2008. The result derived from network analysis was applied to measure the efficiency of programs by Data Envelopment Analysis. The result shows that the weaker network produces higher efficiency as much as the research result itself. Along with the expertise of evaluators themselves, this paper implies that network should be considered as a main item for evaluation.

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U.S. GENERATION IV REACTOR INTEGRATED MATERIALS TECHNOLOGY PROGRAM

  • Corwin William R.
    • Nuclear Engineering and Technology
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    • v.38 no.7
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    • pp.591-618
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    • 2006
  • An integrated R&D program is being conducted to study, qualify, and in some cases, develop materials with required properties for the reactor systems being developed as part the U.S. Department of Energy's Generation IV Reactor Program. The goal of the program is to ensure that the materials research and development (R&D) needed to support Gen IV applications will comprise a comprehensive and integrated effort to identify and provide the materials data and its interpretation needed for the design and construction of the selected advanced reactor concepts. The major materials issues for the five primary systems that have been considered within the U.S. Gen IV Reactor Program-very high temperature gas-cooled, supercritical water-cooled, gas-cooled fast spectrum, lead-cooled fast spectrum, and sodium-cooled fast spectrum reactors-are described along with the R&D that has been identified to address them.

U.S. FUEL CYCLE TECHNOLOGIES R&D PROGRAM FOR NEXT GENERATION NUCLEAR MATERIALS MANAGEMENT

  • Miller, M.C.;Vega, D.A.
    • Nuclear Engineering and Technology
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    • v.45 no.6
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    • pp.803-810
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    • 2013
  • The U.S. Department of Energy's Fuel Cycle Technologies R&D program under the Office of Nuclear Energy is working to advance technologies to enhance both the existing and future fuel cycles. One thrust area is in developing enabling technologies for next generation nuclear materials management under the Materials Protection, Accounting and Control Technologies (MPACT) Campaign where advanced instrumentation, analysis and assessment methods, and security approaches are being developed under a framework of Safeguards and Security by Design. An overview of the MPACT campaign's activities and recent accomplishments is presented along with future plans.

Neutronics analysis of TRIGA Mark II research reactor

  • Rehman, Haseebur;Ahmad, Siraj-ul-Islam
    • Nuclear Engineering and Technology
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    • v.50 no.1
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    • pp.35-42
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    • 2018
  • This article presents clean core criticality calculations and control rod worth calculations for TRIGA (Training, Research, Isotope production-General Atomics) Mark II research reactor benchmark cores using Winfrith Improved Multi-group Scheme-D/4 (WIMS-D/4) and Program for Reactor In-core Analysis using Diffusion Equation (PRIDE) codes. Cores 133 and 134 were analyzed in 2-D (r, ${\theta}$) and 3-D (r, ${\theta}$, z), using WIMS-D/4 and PRIDE codes. Moreover, the influence of cross-section data was also studied using various libraries based on Evaluated Nuclear Data File (ENDF/B-VI.8 and VII.0), Joint Evaluated Fission and Fusion File (JEFF-3.1), Japanese Evaluated Nuclear Data Library (JENDL-3.2), and Joint Evaluated File (JEF-2.2) nuclear data. The simulation results showed that the multiplication factor calculated for all these data libraries is within 1% of the experimental results. The reactivity worth of the control rods of core 134 was also calculated with different homogenization approaches. A comparison was made with experimental and reported Monte Carlo results, and it was found that, using proper homogenization of absorber regions and surrounding fuel regions, the results obtained with PRIDE code are significantly improved.

iKSNF, the Control Tower for the R&D Program of SNF Storage and Disposal

  • Kim, Kyungsu
    • Journal of Nuclear Fuel Cycle and Waste Technology(JNFCWT)
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    • v.20 no.2
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    • pp.255-258
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    • 2022
  • Three government bodies, that is, the Ministry of Science and ICT (MSIT), Ministry of Trade, Industry, and Energy (MOTIE), and Nuclear Safety and Security (NSSC), jointly established the Institute for Korea Spent Nuclear Fuel (iKSNF) in December 2020 to secure the management technologies for spent nuclear fuel (SNF). The objective of iKSNF is to successfully conduct the long-term research and development program of the 「Development of Core Technologies to Ensure Safety of Spent Nuclear Fuel Storage and Disposal System」. Our program, known as the first multi-ministry program in the nuclear field of Korea, mainly focuses on developing core technologies required for the long-term management of SNF, including those for safe storage and deep geological disposal of SNF. The program comprises three subprograms and seven key projects covering the storage, disposal, and regulatory sectors of SNF management. Our program will last from 2021 through 2029, with a budget of approximately four billion USD sponsored by MSIT, MOTIE, and NSSC.

Development of Dual Reporter System of Mutant Dopamine 2 Receptor ($D_2R$) and Sodium Iodide Symporter (NIS) Transgenes (변이 도파민 2 수용체와 나트륨 옥소 공동 수송체 이입유전자의 이중 리포터시스템 개발)

  • Hwang, Do-Won;Lee, Dong-Soo;Kang, Joo-Hyun;Chang, Young-Soo;Kim, Yun-Hui;Jeong, Jae-Min;Chung, June-Key;Lee, Myung-Chul
    • The Korean Journal of Nuclear Medicine
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    • v.38 no.4
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    • pp.294-299
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    • 2004
  • Purpose: Both human NIS and mutant $D_2R$ transgenes are proposed as reporting system in transplanted cell tracking. Using hepatoma cell lines, we constructed a dual reporter system containing human sodium-iodide symporter (hNIS) and dopamine 2 receptor ($D_2R$) and compared its characteristics. Materials and Methods: The recombinant plasmid ($pIRES-hNIS/D_2R$) was constructed with IRES (internal ribosome entry site) under control of the CMV promoter $pIRES-hNIS/D_2R$ was transfected to human hepatoma SK-Hep1 cell line with lipofectamine. HEP-ND ($SK-Hep1-hNIS/D_2R$) cells stably expressing hNIS and $D_2R$ was established by selection with G418 for two weeks. RT-PCR was performed to investigate the expression of both hNIS and $D_2R$ genes. The expressions of hNIS and $D_2R$ were measured by $^{125}I$ uptake assays and receptor binding assays. Specific binding of $D_2R$ to $[^3H]spiperone$ was verified by Scatchard plot with (+) butaclamol as a specific inhibitor. $K_d\;and\;B_{max}$ values were estimated. The correlation between hNIS and $D_2R$ expression was compared by using each clone. Results: Similar quantities of hNIS and $D_2R$ genes were expressed on HEP-ND as RT-PCR assays. HEP-ND cells showed 30 to 40 fold higher radioiodine uptakes than those of parental SK-Hep1 cells. $^{125}I$ uptake in HEP-ND cells was completely inhibited by $KClO_4$, a NIS inhibitor Specific binding to HEP-ND cells was saturable and the $K_d\;and\;B_{max}$ values for HEP-ND cells were 2.92 nM, 745.25 fmol/mg protein and 2.91nM, 1323 fmole/mg protein in two clones, respectively. The radioiodine uptake by hNIS activity and $D_2R$ binding was highly correlated. Conclusion: We developed a dual positron and gamma imaging reporter system of hNIS and $D_2R$ in a stably transfected cell line. We expect that $D_2R$ and hNIS genes can complement mutually as a nuclear reporting system or that $D_2R$ can be used as reporter gene when hNIS gene were used as a treatment gene.

Teleoperation R&D activities in korean nuclear waste program

  • Bum, T.J.;Jung, W.T.;Lee, J.S.
    • 제어로봇시스템학회:학술대회논문집
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    • 1989.10a
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    • pp.795-798
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    • 1989
  • This paper presents some results of teleoperation R&D activities for radioactive work. Heavy power manipulator feature is integrated with vision system implementation of advanced type and tool adaptation to hand gripper. Some assodiated te datth activities of interests to the teleoperation and future directions are also presented.

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PROSPECTIVE ON DEVELOPMENT OF NUCLEAR POWER AND THE ASSOCIATED FUEL CYCLE IN CHINA

  • Gu Zhongmao;Liu Changxin;Fu Manchang
    • Proceedings of the Korean Radioactive Waste Society Conference
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    • 2005.11b
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    • pp.156-164
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    • 2005
  • The challenges China is facing in energy security are briefly discussed. Then, the development of nuclear power in China in the first half of 21 st century is envisioned, and it is expected that Generation-3 PWR nuclear power plants (NPPs) would be the leading units of nuclear power in the coming $30\~40$ years. As part of the nuclear power program, the R&D work on nuclear fuel cycle is generally proposed.

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