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1
Corrosion in Water Moderated Nuclear Power Plants.
1976-01-01

In this report, the main problems connected to corrosion failures of the structural materials of water cooled nuclear reactors are described. (Atomindex citation 08:337139)

National Technical Information Service (NTIS)

2
Power-Up of Fugen Reactor and Development of Demonstration Plant.
1979-01-01

The Fugen Nuclear Power Station is the 165 MWe prototype plant characterized by heavy water-moderated, boiling light water-cooled, pressure tube type, and was developed by the Power Reactor and Nuclear Fuel Development Corporation, Japan. The plant went i...

National Technical Information Service (NTIS)

3
ECONOMICS OF HEAVY WATER POWER REACTORS
1962-10-01

Three types of the heavy-water-moderated power reactor that are part of the Canadian development program for nuclear power are discussed. Competitive sources of power and the place for nuclear power in Canadian utility systems are suggested. The interest of other countries in heavywater ...

Energy Citations Database

4
ENGINEERING STUDIES HEAVY WATER MODERATED POWER REACTOR PLANTS
1963-06-30

Design and economic aspects of 300-, 500-, and 1000Mw(e) heavy water- moderated power reactors are illustrated and the computer codes used in the analyses are discussed. The plant concepts all use pressure tube type reactors with cold heavy water as moderator and are cooled by: liquid heavy water, boiling heavy water, organic ...

Energy Citations Database

5
Semi-Empirical Evaluation Studies on PCMI for the Fugen Fuel Rod.
1980-01-01

Fugen, 165 MWe prototype of a heavy water moderated boiling water cooled reactor, has been well operated since March 1979. In order to establish PCIOMR for Fugen fuels semi-empirical evaluation code to analyze PCMI during power transient of the fuel rod h...

National Technical Information Service (NTIS)

6
NUCLEAR CALCULATION FOR LIGHT WATER MODERATED REACTOR. Report No. 4
1958-03-01

ABS>Calculation methods are presented for light water cooled and moderated power reactors. Three and four group theory are used taking into account the effect of epithermal fission. Results on four factor, multiplication factor, Fermi age and buckling of UO/sub 2/ fueled reactors, effectiveness of control rods, and long ...

Energy Citations Database

7
UVR-1200 - a new-generation high-capacity power-generating unit
1995-10-01

A new-generation high-capacity power-generating unit based on an improved water-moderated water-cooled UVR-1200 reactor is being developed with the idea of producing a large series of standardized units which would replace the power-generating capacity that has been shut down and would expand the production of ...

Energy Citations Database

8
Development of Automatic Ultrasonic Remote-Controlled In ...

... water moderated, light-water cooled, vertical pressure tube type reactor. ... Basic technologies for in-service inspection equipment were manufactured ...

DTIC Science & Technology

9
Supercritical water cooled reactors
2008-05-01

The main advantages of implementation of water-moderated water-cooled power reactors with supercritical parameters in power engineering are shown.

NASA Astrophysics Data System (ADS)

10
Full scale safety experiments of pressure tube type reactor. Heavy water moderated boiling light water cooled reactor
1972-01-01

From international nuclear industries fair; Basel, Switzerland (16 Oct 1972). Results on the blowdown testing of the FUGEN heavy water moderated boiling light water cooled reactor carried out in the full scale safety experimental facility at PNC are presented. (auth)

Energy Citations Database

11
INVESTIGATION OF REACTOR TRANSIENTS AND POWER PATTERNS OF A HEAVY WATER- MODERATED, BOILING HEAVY WATER-COOLED REACTOR
1961-03-21

Studies were made of the possibility of reactor instability and flux pattern perturbations in boiling D/sub 2/O-modarated reactors due to the small but positive coolant void coeffidient. The results for constant reactor inlet conditions indicats that a positive coolant void coefficient up to twice the calculated values does not introduce any serious control problems for either the ...

Energy Citations Database

12
Conceptual design of a water cooled reactor with passive decay heat removal. Final performance technical report, September 30, 1992--October 31, 1995
1996-11-19

A conceptual design was performed of a light water moderated reactor with power output in the range of 1000 MWe, which allows passive decay heat removal (i.e., the heat path to the ultimate heat sink, ambient air, is provided by natural heat transfer mechanisms such as conduction, radiation and free convection). This eliminates the ...

DOE Information Bridge

13
NON-STATIONARY HEAT CONDUCTION IN HEAT-PRODUCING ELEMENTS OF A NUCLEAR REACTOR
1961-05-01

The transient heat conduction in a water cooled, water moderator reactor is solved by a Laplace transform method. The results are correlated with data obtained on a hydraulic analog computer. (tr-auth)

Energy Citations Database

14
NEW NUCLEAR REACTOR
1962-11-01

ABS>Descriptions are given of a new water-cooled, water moderated research reactor IRT-2000 in Salaspilis, Latvia. A gamma source (30 kg equiv Ra) is developed through the use of a liquid indium-gallium -tin loop. (R.V.J.)

Energy Citations Database

15
Department of Energy's team's analyses of Soviet designed VVERs. Revision 1, Main report.
1989-01-01

The purpose of this report is to summarize the results of the US Department of Energy (DOE) Analysis Team's analyses of Soviet designed VVERs (Water-cooled, Water-moderated Energy Reactor). The principle objective of this undertaking is to provide a basis...

National Technical Information Service (NTIS)

16
Advanced Neutron Source: Plant Design Requirements. Revision 4.
1990-01-01

The Advanced Neutron Source will be a new world-class facility for research using hot, thermal, cold, and ultra-cold neutrons. The heart of the facility will be a 330-MW (fission), heavy-water cooled and heavy-water moderated reactor. The reactor will be ...

National Technical Information Service (NTIS)

17
CANADA-INDIA REACTOR
1960-09-01

The Canada-India Reactor is a natural-uranium-fueled heavy-water- moderated light-water-cooled reactor with a power of 40 Mw. The reactor is housed in a pressure shell of steel, 120 ft in diameter and 134 ft high. The reactor vessel is an aluminum tank 8 ft 9 in. in diameter and 11 ft high. Two cast iron ...

Energy Citations Database

18
ATOMIC SCIENCE AND TECHNIQUE AND BUILDING OF COMMUNISM
1961-10-01

Atomic energy, being a highly concentrated source, contributd directly to the coverage of the energy needs of the Soviet population. Radioisotopes were used to automate many industrial processes and found many applications in science and medicine. The first atomic power station in the world operated continuously for 7 years at a power level ot ...

Energy Citations Database

19
Evolution of service to the power reactor community at the UFTR - beyond the bottom line
1993-01-01

The University of Florida Training Reactor (UFTR) is a 100-kW light-water-cooled, graphite-and-light-water-moderated modified argonaut-type reactor. Although currently fueled with highly enriched (93% [sup 235]U) fuel, analyses are nearly completed for conversion to low-enriched fuel. The core design consists of individual fuel boxes in each of which flow ...

Energy Citations Database

20
Research in the discharge of radionuclides to the atmosphere and assessment of the maximum permissible discharges in the context of the reprocessing of nuclear power plant fuel elements
1986-02-01

The authors present results of research in the atmospheric discharge of fission and neutron-activation products, and also of transuranium elements (TE) which were obtained during the operation of facilities for recycling spent VVER (water-moderated, water-cooled power reactor) fuel elements. The activity of the TE in the fuel was ...

Energy Citations Database

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21
High Power Cable with Internal Water Cooling 400 Kv.
1982-01-01

Due to the concentration of electricity production in large power plants, the need of higher power transmissions, and the protection of environment, developement of a 400 kV water cooled cable in the power range of 1 to 5 GVA was undertaken. The fabricati...

National Technical Information Service (NTIS)

22
High Power Underground Cable System with Direct Water Cooling.
1984-01-01

Research object is a high power underground cable with direct water-cooling, developed by F and G Carlswerk AG and K and D Lackdrahtfabriken. The objective is to show its suitability for bulk power transmission in densely built-up areas. Additionally, cor...

National Technical Information Service (NTIS)

23
Trace-element characterization of evidential cannabis sative samples using k{sub 0}-standardization methodology
1995-12-31

The University of Florida Training Reactor (UFTR) facilities including the analytical laboratory are used for a wide range of educational, research, training, and service functions. The UFTR is a 100-kW light-water-cooled, graphite-and-water-moderated modified Argonaut-type reactor. The UFTR utilizes high enriched plate-type fuel in a two-slab arrangement ...

Energy Citations Database

24
Sensitivity Degradation Characteristics of In-core Neutron Detector for Heavy Water Reactor, Fugen NPP
2002-07-01

Fugen nuclear power plant is a 165 MWe, heavy water-moderated, boiling light water-cooled, pressure tube-type reactor developed by JNC, which is the world's first thermal neutron power reactor to utilize mainly Uranium and Plutonium mixed oxide (MOX) fuel. Fugen has been loaded a total of 726 MOX fuel ...

Energy Citations Database

25
Occupational Radiation Exposure at Light Water Cooled Power Reactors, 1969--1974.
1975-01-01

This report presents an updated compilation of occupational radiation exposures at commercial light water cooled power reactors for the years 1969 through 1974. The information is derived from reports submitted to the United States Nuclear Regulatory Comm...

National Technical Information Service (NTIS)

26
Mathematical Model for Studying Boiling Water Cooled Reactor Power Resonance Instability.
1982-01-01

The mathematical model of dynamics of a tank type boiling water cooled reactor with natural circulation is developed. The reactor is represented as a system with feedback taking into account void and Doppler reactivity effects. Calculation of the power ef...

National Technical Information Service (NTIS)

28
Single failure effects on surge line break transients for the VVER-440 reactor
1992-01-01

This paper describes the analysis of surge line break transients for the soviet designed, water cooled, light water moderated, power reactors referred to as VVERS. These events represent an intermediate size loss of coolant accident (LOCA) for these plants and provide a severe challenge to the ...

Energy Citations Database

29
Single failure effects on surge line break transients for the VVER-440 reactor
1992-09-01

This paper describes the analysis of surge line break transients for the soviet designed, water cooled, light water moderated, power reactors referred to as VVERS. These events represent an intermediate size loss of coolant accident (LOCA) for these plants and provide a severe challenge to the ...

Energy Citations Database

30
^ Ris� Report No. 373r o

WATER COOLED REACTORS WATER MODERATED RFACTORS ZIRCALOY UDC 621,039,548 : 681.3.06 : 519.283 #12;Ris� irradiation conditions. Models describing the im- portant material properties for zircaloy, U02� and the gap 44 #12;Page 5.3.2. Gap conductance 45 5.3.3. Creep in fuel and cladding 47 5.3.4. Hot swelling

E-print Network

31
Seismicity and Seismic Response of the Soviet-Designed VVER (Water-Cooled, Water Moderated Energy Reactor) Reactor Plants.
1989-01-01

On March 4, 1977, a strong earthquake occurred at Vrancea, Romania, about 350 km from the Kozloduy plant in Bulgaria. Subsequent to this event, construction of the unit 2 of the Armenia plant was delayed over two years while seismic features were added. O...

National Technical Information Service (NTIS)

32
SOME CIVIL ENGINEERING ASPECTS OF THE CANADA INDIA REACTOR PROJECT
1961-01-01

Civil engineering aspects of the construction of the Canada Indin Reactor (CIIR)are reviewed. The CIR is a nathnal U, heavy water moderated, light water cooled research reactor. The reactor site is near the sea and as much as 14 ft below sea level, necessitating waterproofing of foundations. Measures and ...

Energy Citations Database

33
Physical Characteristics of the Irt-2000 Swimming-Pool Research Reactor with Loop Channels (Fizichnyya Kharaktarystyki Dasledchaga Reaktara Baseinavaga Typu Irt-2000 Z Petlyavym Kanalam).
1968-01-01

The IRT-2000 reactor installed in the Institute of Heat and Mass Exchange of the Academy of Sciences of the Belorussian SSR was put in operation in May 1962. Water-cooled water-moderated reactors of the IRT type are simple in design, highly reliable, and ...

National Technical Information Service (NTIS)

34
Effect of 0.3eV resonance cross section for plutonium on coolant void reactivity in heavy water lattice.
1996-01-01

Plutonium fuel could be utilized in the entire core of heavy water moderated, boiling light water cooled pressure-tube-type reactor (HWR). The void reactivity, however, depends on the various parameters of the lattice. It is especially significant to clar...

National Technical Information Service (NTIS)

35
ENGINEERING EVALUATION STUDIES, HEAVY WATER MODERATED POWER REACTOR PLANTS
1962-06-30

Results of a series of engineering evaluation studies related to heavy water moderated power reactor plants are discussed. Results indicate that boiling D/sub 2/O direct cycle plants can produce power more cheaply than any other type of D/sub 2/O moderated system. A program is in progress to develop a ...

Energy Citations Database

36
Prospects for development of nuclear power stations equipped with VVER reactors
2011-05-01

The prospects for further development in Russia of nuclear stations equipped with water-cooled water-moderated reactors are considered.

NASA Astrophysics Data System (ADS)

37
ANP HTREs FULFILL TEST GOALS
1961-01-01

Performance results from the Heat Transfer Reactor Experiment (HTBE) test series have measured up to or exceeded expectations. The series has involved three reactor systems (HTRE-l, HTRE-2, and HTRE-3) and two reactor concepts (water-moderated and ZrH-moderated). HTRE-l achieved a number of full- power runs which demonstrated conclusively the ...

Energy Citations Database

38
Demineralised water cooling in the LHC accelerator

In spite of the LHC accelerator being a cryogenic machine, it remains nevertheless a not negligible heat load to be removed by conventional water-cooling. About 24MW will be taken away by demineralised water cooled directly by primary water from the LHC cooling towers placed at the even points. This paper describes the demineralised ...

E-print Network

39
Trends in the Application of Titanium Tubes in Sea Water ...

... Abstract : Many millions of titanium tubes have been installed in sea-water cooled condensers, evaporators, and coolers in the power, oil and ...

DTIC Science & Technology

40
Thermal-Fluid Analysis and Simulation of High Power Solid ...
2002-06-01

... The solid-state diode array in an H-package using a conventional water-cooling flow was analyzed using a combined thermal and fluid finite ...

DTIC Science & Technology

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41
The use of experimental data in an MTR-type nuclear reactor safety analysis
2006-01-01

Reactivity initiated accidents (RIAs) are a category of events required for research reactor safety analysis. A subset of this is unprotected RIAs in which mechanical systems or human intervention are not credited in the response of the system. Light-water cooled and moderated MTR-type ( i.e., aluminum-clad uranium plate fuel) reactors are self-limiting up ...

NASA Astrophysics Data System (ADS)

42
Seismicity and seismic response of the Soviet-designed VVER (Water-cooled, Water moderated Energy Reactor) reactor plants
1989-01-01

On March 4, 1977, a strong earthquake occurred at Vrancea, Romania, about 350 km from the Kozloduy plant in Bulgaria. Subsequent to this event, construction of the unit 2 of the Armenia plant was delayed over two years while seismic features were added. On December 7, 1988, another strong earthquake struck northwest Armenia about 90 km north of the Armenia plant. Extensive damage of residential ...

Energy Citations Database

43
Review of High Temperature Water and Steam Cooled Reactor Concepts
2002-07-01

This review summarizes design concepts of supercritical-pressure water cooled reactors (SCR), nuclear superheaters and steam cooled fast reactors from 1950's to the present time. It includes water moderated supercritical steam cooled reactor, SCOTT-R and SC-PWR of Westinghouse, heavy ...

Energy Citations Database

44
Reactor Physics Measurements with 19-Element ThOsub(2)-Sup (235)UOsub(2) Cluster Fuel in Heavy Water Moderator.
1985-01-01

Low power lattice physics measurements have been performed with a single rod of 19-element thorium oxide fuel enriched with 1.45 wt. percent sub(235)UOsub(2) (93 percent enriched) in a simulated heavy water moderated and cooled power reactor core. The exp...

National Technical Information Service (NTIS)

45
ENGINEERING EVALUATION STUDIES--HEAVY WATER MODERATED POWER REACTOR PLANTS. Quarterly Progress Report, July-September 1961
1961-10-13

Activities in a study program concerned with heavy water moderated reactor plants are summarized. The study is centered around a computer program for economic optimization of D/sub 2/0 power reactors, and prototype scoping. Data are included on costs for direct and indirect cycle turbine plants, and design criteria are listed ...

Energy Citations Database

46
PM RESEARCH AND DEVELOPMENT--TASK 1.0--CORE 2 REFERENCE DESIGN REPORT
1962-08-01

The reference design of Core 2, which is being designed primarily as a replacement core for the PM-1 and PM-3A nuclear power plants is described. In addition, the thermal and hydraulic capabilities were investigated; these indicated applicability of the core to higher powered PM-type plants. Core 2, like the first generation cores, utilizes fully ...

Energy Citations Database

47
Numerical analysis on the beam quality improvements of high power chemical laser system with water cooled mirrors
2011-06-01

Chemical laser is one of the most widely used high power infrared sources. Thermal deformation of mirrors in a resonator is a key factor which hinders the improvement of the beam quality in high power chemical lasers, and it has been a matter of the utmost concern in the design of high power chemical laser systems. ...

NASA Astrophysics Data System (ADS)

48
High Average Power Laser Amplifier Chain Techniques.
1970-01-01

The report describes the results obtained in the development of a high average power optical radar transmitter operating at 1.06 microns employing a master oscillator-power amplifier approach. The master oscillator was a mode controlled, water-cooled, pul...

National Technical Information Service (NTIS)

49
HEAVY WATER MODERATED REACTORS EVALUATION STUDY. VOLUME III. PLANT DESIGNS
1962-10-15

Detailed descriptions of a boiling heavy water reactor plant, a gas- cooled heavy water moderated reactor plant, and a pressurized heavy water reactor plant are presented. The information is given as a part of the comparative evaluation of large nuclear electric power generating plants. (J.R.D.)

Energy Citations Database

50
Multipurpose Outage at a Midsize, Resource-Limited Nonpower Reactor
2000-06-04

The University of Florida Training Reactor (UFTR) is a light water-cooled, graphite and light water-moderated, modified Argonaut-type reactor licensed to operate at steady-state power levels up to 100 kW. The UFTR was subject to a unique and lengthy voluntary outage beginning in May 1998 following several months of gradual increases in ...

Energy Citations Database

51
Experience from Construction and Operation of Karachi Nuclear Power Plant.
1977-01-01

Pakistan's first nuclear power plant (KANUPP) is owned and operated by the Pakistan Atomic Energy Commission (PAEC). It uses a heavy water moderated and cooled natural uranium fuelled reactor. Total installed capacity is 137 MW(e). It was designed, constr...

National Technical Information Service (NTIS)

52
Continued Development of the Quandry Code.
1984-01-01

The general goal of the work carried out has been to develop and test a method for predicting detailed power history throughout the lifetime of a light water moderated power reactor. The authors have based the scheme on the two-group nodal code QUANDRY, a...

National Technical Information Service (NTIS)

53
Unconventional Nuclear Power Plant Siting Options and Water Resource Impacts.
1975-01-01

A technology assessment of three unconventional power plant siting options: floating nuclear plants, plants using salt-water cooling towers, and underground nuclear plants was undertaken. Floating nuclear plants have some environmental benefits, less land...

National Technical Information Service (NTIS)

54
Gamma Spectroscopy in Water Cooled Reactors.
1977-01-01

Gamma spectroscopy analysis of spent fuels in power reactors is described for two typical cases: determination of the power distribution by the mean of the activity of a low periodic element (Lanthanum 140) and determination of the burnup absolute rate by...

National Technical Information Service (NTIS)

55
Bright Source Energy Inc. Oakland, California
2007-04-17

Electric Natural Gas Gas-Fired Boiler 140 Bar Water Cooling Condenser Generator Steam Turbine Solar Tower Receiver Power Block Solar Field DPT 550 Power Generation Schematic 9...

National Renewable Energy Laboratory (NREL)

56
The Environmental Behavior of Transuranic Nuclides Released from Water Cooled Nuclear Power Plants.
1981-01-01

Release data are reported for three coastal water-cooled nuclear reactors: Millstone Point No. 1 and No. 2 (for the period January 1977 through April 1978), and Maine Yankee (for the period 20 June 1977 through 25 March 1978); release samples were analyze...

National Technical Information Service (NTIS)

57
Doublet III limiter/armor update
1983-12-01

The Doublet III device is operating with an extensive system of plasma limiters and wall protective armor. Operations with up to 8MW of neutral beam power and 1.5MA plasma current are planned. Design and operational performance of the following systems are discussed: 1. Water-cooled graphite moveable limiter. 2. Water-cooled graphite ...

Energy Citations Database

58
ORGANIC MODERATORS AND COOLANTS
1960-01-01

Problems of using organic moderators and coolants for nuclear reactors are discussed and criteria for the choice of organic materials are presented. Property changes of the compounds caused by radiation and heating are presented. Tbe Organic Moderated Reactor Experiment and the Canadian heavy water moderated power reactor ...

Energy Citations Database

59
Neutron Spectra in WWER Reactor Lattices.
1975-01-01

The authors analyze the epithermal and thermal portions of the energy spectrum of neutrons in the lattices of water-cooled, water-moderated power reactors based on experimentally determined spectral indices of eight isotopes. The obtained values of the th...

National Technical Information Service (NTIS)

60
Heavy Water and Nonproliferation.
1980-01-01

This report begins with a historical sketch of heavy water. The report next assesses the nonproliferation implications of the use of heavy water-moderated power reactors; several different reactor types are discussed, but the focus is on the natural urani...

National Technical Information Service (NTIS)

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61
Heavy Water Moderated Organic Cooled Nuclear Fission Reactor.
1965-01-01

An organic liquid cooled D20 moderated nuclear reactor is provided which has reduced neutron losses. The reactor is designed to produce power. A unique arrangement is disclosed in which no excess reactivity is provided which has to be controlled during st...

National Technical Information Service (NTIS)

62
DETERMINATION OF HEAVY WATER PURITY BY INFRARED ABSORPTION
1962-01-16

The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)

Energy Citations Database

63
Criticality evaluation and protocol for DOE-owned spent nuclear fuels.
1995-01-01

This report is a continuation of repository criticality evaluation work. Both the probability and consequences of a criticality were considered. A long-term, low-power, water-moderated criticality was the most likely of those considered. Its probability w...

National Technical Information Service (NTIS)

64
Calculations on Heavy-Water Moderated and Cooled Natural Uranium Fuelled Power Reactors.
1979-01-01

One of the codes that the Instituto Nacional de Investigaciones Nucleares (Mexico) has for the nuclear reactors design calculations is the LEOPARD code. This work studies the reliability of this code in reactors design calculations which component materia...

National Technical Information Service (NTIS)

65
The design of a new coaxial water cooling structure for APS high power BM front end photon shutters
1993-07-01

A new UHV compatible coaxial water cooling structure has been designed for Advanced Photon Source (APS) high power bending magnet front end photon shutters. Laser-beam-thermal-simulation test results show that this new cooling structure can provide more than 1.56 kW total power cooling capacity with 12.3 W/mm{sup ...

DOE Information Bridge

66
RADIATION PROTECTION CONSIDERATIONS IN A HEAVY WATER MODERATED REACTOR
1958-10-31

erce on the Peaceful Uses of Atomic Energy, 1958. Radiation protection problems are reviewed for a heavy-water moderated, heavy-water-cooled, naturaluranium fueled reactor. The importance of and methods used in moderator purification and the characteristic radioisotopes encountered are mentioned. The following are discussed: ...

Energy Citations Database

67
Expanding reactor facility usage for public education about nuclear energy
1995-12-31

The University of Florida training reactor (UFTR) is a 100-kW light-water-cooled, graphite-and-light-water-moderated argonaut-type university reactor in a loop configuration. Since first licensed at 10 kW in 1959 and then at the present 100kW limit in 1969, this facility within the nuclear engineering sciences department has been actively involved in a ...

Energy Citations Database

68
Flow Stability of Supercritical Water Cooled Systems
2006-07-01

Research activities are ongoing worldwide to develop nuclear power plants with supercritical water cooled reactor (SCWR) with the purpose to achieve a high thermal efficiency and to improve their economical competitiveness. However, the strong variation of the thermal-physical properties of water in the vicinity of the pseudo-critical ...

Energy Citations Database

69
Radioactive Effluents and Present and Future Radiation Exposure to the Population from Nuclear Facilities in the Federal Republic of Germany.
1977-01-01

At this time ten light water cooled nuclear power plants are operated outside of nuclear research centers in the Federal Republic of Germany. A review of the releases of radioactivity in gaseous and liquid effluents shows that increasing operational exper...

National Technical Information Service (NTIS)

70
Phenomenology of Deflagration and Detonation of Hydrogen-Air Mixtures in Water Cooled Nuclear Power Plants.
1984-01-01

This paper summarizes fundamentals of the flammability of the hydrogen-air mixtures and hydrogen-air containing added steam or other inerting agent. The flammability behaviour of such gaseous mixtures is described with reference to physical and chemical c...

National Technical Information Service (NTIS)

71
Means of Examination and Evaluation of Fuel Assembly for Water Cooled Power Reactors in the Nuclear Research Center at Saclay (CEA).
1984-01-01

Description is presented of the equipment of two laboratories at Saclay (CEA) concerned with destructive and nondestructive experiences on spent fuels from pressurized water reactors in France. Study of fuel assemblies in fuel storage pools, study of fuel...

National Technical Information Service (NTIS)

72
Matrix effects in inductively coupled plasma mass spectrometry.
1995-01-01

The inductively coupled plasma is an electrodeless discharge in a gas (usually Ar) at atmospheric pressure. Radio frequency energy generated by a RF power source is inductively coupled to the plasma gas through a water cooled load coil. In ICP-MS the (ope...

National Technical Information Service (NTIS)

73
Integrated Leak Rate Testing for Containment Integrity.
1978-01-01

Prior to the receipt of an operating license in the United States for all water-cooled power reactors, a primary containment integrated leak rate test (ILRT) must be performed. This test must satisfy the requirements as outlined in the Code of Federal Reg...

National Technical Information Service (NTIS)

74
Hydrogen in Water-Cooled Nuclear Reactors.
1987-01-01

This paper summarizes a report that reviews the knowledge of hydrogen-related phenomena considered in the safety assessment of a nuclear power plant having water-cooled nuclear reactors. This involves reviewing experimental results from research programs ...

National Technical Information Service (NTIS)

75
Fuel Cells in Transit Buses Summary

a regenerative braking system. MAN is part of the Clean Energy Partnership Berlin (CEP). CEP was established regenerative braking and either batteries or an ultracapacitor to provide acceleration and extra power water-cooled electric drive motors that serve as regenerative brakes. The fuel cells use compressed

E-print Network

76
Evaluation of Models for Predicting Evaporative Water Loss in Cooling Impoundments.
1982-01-01

Cooling impoundments can offer a number of advantages over cooling towers for condenser water cooling at steam electric power plants. However, a major disadvantage of cooling ponds is a lack of confidence in the ability to predict various aspects of their...

National Technical Information Service (NTIS)

77
Critical Heat Flux in Subcooled and Low Quality Boiling.
1976-01-01

A semi-empirical relationship for critical heat flux prediction in a light water cooled power reactor core is developed. The method of developing this relationship is the extension of the analysis of pool boiling crisis for forced convective boiling. In t...

National Technical Information Service (NTIS)

78
Computerized Engineering Model for Evaporative Water Cooling Towers.
1977-01-01

The evaporative cooling tower is often used to reject waste heat from industrial processes, especially power plants and chemical facilities. A consistent physical model for crossflow and counterflow cooling towers which imposes rigorous heat and mass bala...

National Technical Information Service (NTIS)

79
Code Case acceptability, ASME section III materials. [BWR; PWR
1976-05-01

A listing is given of those Section 3 ASME code cases oriented to materials and testing that are generally acceptable to the NRC staff for implementation in the licensing of light-water cooled nuclear power plants.

Energy Citations Database

80
Catalog of experimental projects for a fissioning plasma reactor
1973-06-01

Experimental and theoretical investigations were carried out to determine the feasibility of using a small scale fissioning uranium plasma as the power source in a driver reactor. The driver system is a light water cooled and moderated reactor of the MTR type. The eight experiments and proposed configurations for the reactor ...

Energy Citations Database

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81
About the Author Data Centers

of this direct water cooling must be designed with the rack vendor in advance of installation. Some solutions that exist in the computer industry for years do not address communication equipment specific design issues for the industry to create a new design and architecture space to address the power-density challenges of next

E-print Network

82
A Two-Phase Cooling Loop for Fission Surface Power Waste Heat ...

Sep 18, 2009 ... The current approach is to transport waste heat using a heavy, pressurized water cooling loop. For each 20 kW of heat rejection, ...

NASA Website

83
A Survey of Alternate Methods for Cooling Condenser Discharge Water. System, Selection, Design, and Optimization.
1971-01-01

A computer program was written to calculate cooling system and power plant cost and to determine the minimum total cost for a given set of parameters. Design equations based on the use of water cooled condensers, cooling towers, open cooling systems, oper...

National Technical Information Service (NTIS)

84
CIVILIAN POWER REACTOR PROGRAM. PART II. ECONOMIC POTENTIAL AND DEVELOPMENT PROGRAM AS OF 1959
1960-01-01

The status of technology of nuclear power reactors in 1959 is reviewed. General research and engineering development activities are discussed. The reactors considered include the pressurized water, boiling water, light water moderated superheat, organic cooled, sodium graphite, gas cooled enriched fuel, gas cooled natural ...

DOE Information Bridge

85
Pressure loadings of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) reactor release mitigation structures from large-break LOCAs
1989-01-01

Analyses have been carried out of the pressurization of the accident release mitigation structures of Soviet-designed VVER (Water-Cooled, Water-Moderated Energy Reactor) pressurized water reactors following large-break loss-of-coolant accidents. Specific VVER systems for which calculations were performed are the VVER-440 model V230, VVER-440 model V213, ...

DOE Information Bridge

86
HEAVY WATER MODERATED POWER REACTOR PLANTS DESIGN STUDY--SUMMARY OF PARTS 1- 3
1959-06-01

A design study of heavy-water-moderated power reactor plants is summarized. The over-all study had two objectives: selection and recommendation of a conceptual design of a heavy water moderated power reactor plant providing optimum economics with slight fuel enrichment, but capable of operating with ...

Energy Citations Database

87
POWER REACTOR STUDIES. Quarterly Progress Report for August, September, and October 1957
1958-02-01

An evaluation is made of gas cooling versus heavy water cooling for power reactors that are fueled with natural uranium metal and moderated with heavy water. The power reactors are designed to produce 100 Mwe. Basic physics data, engineering design problems, metallurgical developments, and estimates of ...

Energy Citations Database

88
Continued development of the QUANDRY code. Final report
1984-01-01

The general goal of the work carried out has been to develop and test a method for predicting detailed power history throughout the lifetime of a light water moderated power reactor. The authors have based the scheme on the two-group nodal code QUANDRY, and the present work has been concerned with testing and ...

Energy Citations Database

89
Effectiveness of Four Water Cooled Undergarments and a ...
1975-12-01

... Descriptors : *PROTECTIVE CLOTHING, *WATER COOLING, HEAT TRANSFER, INSULATION, ENVIRONMENTAL PROTECTION, UNDERWEAR ...

DTIC Science & Technology

90
Power spectral density measurements with /sup 252/Cf for a light water moderated research reactor
1979-01-01

A method of determining the reactivity of far subcritical systems from neutron noise power spectral density measurements with /sup 252/Cf has previously been tested in fast reactor critical assemblies: a mockup of the Fast Flux Test Facility reactor and a uranium metal sphere. Calculations indicated that this measurement was feasible for a pressurized water reactor (PWR). In ...

Energy Citations Database

91
EVALUATION AND DESIGN HEAVY WATER MODERATED POWER REACTOR PLANTS
1960-06-30

The 200 and 300 Mw(e) boiling D/sub 2/O direct-cycle plant designs have undergone design revisions which substantially affect their power costs. The revisions resulted from incorporating improvemerts, that were originally made for the 70 Mw(e) direct-cycle prototype plant, into the full-scale plant designs. The results of other studies which relate directly to heavy ...

Energy Citations Database

92
Hybrid liquid metal-water cooling system for heat dissipation of high power density microdevices
2010-12-01

The recent decades have witnessed a remarkable advancement of very large scale integrated circuits (VLSI) and electronic equipments in micro-electronic industry. Meanwhile, the ever increasing power density of microdevices leads to the tough issue that thermal management becomes rather hard to solve. Conventional water cooling is ...

NASA Astrophysics Data System (ADS)

93
The thermal circuit of a nuclear power station's unit built around a supercritical-pressure water-cooled reactor
2010-12-01

Main results obtained from calculations of the steam generator and thermal circuit of the steam turbine unit for a nuclear power unit with supercritical-pressure water coolant and integral layout are presented. The obtained characteristics point to the advisability of carrying out further developments of this promising nuclear power technology.

NASA Astrophysics Data System (ADS)

94
HISTORY AND CURRENT STATUS OF FUEL ELEMENTS FOR POWER REACTORS. Section I of ADVANCED COURSE ON FUEL ELEMENTS FOR WATER COOLED POWER REACTORS
1961-10-31

The advantages and disadvantages of water-cooled power reactors are enumerated, and a brief history of reactor development is outlined. Classification of fuel elements, requirements for nuclear fuel, present status, burn-up, cladding, heat transfer, and reprocessing are discussed. (W.D.M.)

Energy Citations Database

95
FACT BOOK ON U.S. NUCLEAR POWER PROJECTS. Fifth Edition
1963-07-01

A collection is presented of background information on the deveIopment of nuclear electric power in U. S. and of fact sheets on all U. S. power reactor projects, The fact sheets are arranged under the reactor types: water-cooled, sodium-cooled, organic-cooled, and gas-cooled. (D.L.C.)

Energy Citations Database

96
THE EL-4 PROJECT. THE PLACE OF EL-4 IN THE FRENCH PROGRAM. PRESENTATION OF THE EL-4 PRELIMINARY PLAN
1961-11-01

The EL-4 project is a heavy-water moderated and carbon-dioxide cooled power reactor prototype. The reasons that induced the French CEA to investigate this reactor type are discussed. The technical and economic advantages (high power and lower fuel cost) are outlined. The chief characteristics of this ...

Energy Citations Database

97
Preliminary Report on the Promise of Accelerator-Driven Natural-Uranium-Fueled Light-Water-Moderated Breeding Power Reactors.
1977-01-01

A new concept for a power breeder reactor that consists of an accelerator-driven subcritical thermal fission system is proposed. In this system an accelerator provides a high-energy proton beam which interacts with a heavy-element target to produce, via s...

National Technical Information Service (NTIS)

98
Power density flattening in fusion-fission hybrid reactors
1983-05-01

A number of approaches to the design of fusion-fission hybrid reactor blankets having a flat power distribution and constant energy multiplication are described. These include the use of reflectors, lithium control, spectral shift control, and inherent control. These approaches are illustrated for natural-uraniumfueled, light-water-moderated blankets.

Energy Citations Database

99
Power Spectral Density Measurements with exp 252 Cf for a Light Water Moderated Research Reactor.
1979-01-01

A method of determining the reactivity of far subcritical systems from neutron noise power spectral density measurements with exp 252 Cf has previously been tested in fast reactor critical assemblies: a mockup of the Fast Flux Test Facility reactor and a ...

National Technical Information Service (NTIS)

100
POWER-REACTOR FUNDAMENTALS. Paper 2 of SYMPOSIUM ON EQUIPMENT MANUFACTURING AND DEVELOPMENT PROBLEMS FOR NUCLEAR POWER SYSTEMS, CHALK RIVER, ONTARIO, APRIL 19-20, 1960
1960-10-31

Various components of heterogeneous thermal reactors are discussed, and some details of heavy water moderated reactors are given. The NRU Reactor is briefly described. (W.D.M.)

Energy Citations Database

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101
NUCLEAR ELECTRIC POWER--ONE OF THE GIANTS
1962-06-01

A survey of power requirements and potentials for the next 40 years is presented. It is noted that U costs will remain low and a continuing supply is assured. Several types of reactors including natural-U heavy-water-moderated systems seem likely to meet the competition set by largescale plants using conventional fuel. (J.R.D.)

Energy Citations Database

102
Molten fuel-coolant interactions resulting from power transients in aluminium plate/water moderated reactors.
1989-01-01

The behaviour of two reactors SL1 and SPERT D12, which underwent fast nuclear power transients prior to core destruction by a molten fuel-coolant interaction (MFCI) has been analysed and the results compared with measured data. The calculated spatial melt...

National Technical Information Service (NTIS)

103
CIVILIAN POWER REACTOR PROGRAM. PART I. SUMMARY OF TECHNICAL AND ECONOMIC STATUS AS OF 1960. HEAVY WATER-MODERATED POWER REACTORS
1960-08-19

A revision of section 8 of TID-8516, Part I, is presented. The reactor concept which is presented is a change from the former design, a pressurized- pressure vessel-indirect cycle plant to a boiling-pressure tubedirect cycle plant. A description of the plant and a summary of characteristics for the 110- and 325- Mwe systems are given. (J.R.D.)

Energy Citations Database

104
IMPROVED NUCLEAR POWER REACTOR
1964-04-01

A steam-cooled, heavy or light water moderated power reactor is designed. The fuel elements are disposed within the inner tubes of coaxial tube pairs whose outer tubes nt their upper ends are fed with saturated cooling steara aad at their lower ends are closed so that steam passiag through the annulus is passed into the inner ...

Energy Citations Database

105
Unconventional nuclear power plant siting options and water resource impacts. Completion report
1975-12-01

A technology assessment of three unconventional power plant siting options: floating nuclear plants, plants using salt-water cooling towers, and underground nuclear plants was undertaken. Floating nuclear plants have some environmental benefits, less land-use and reduced thermal impact on the marine environment. ...

Energy Citations Database

106
STUDY OF REMOTE MILITARY POWER APPLICATIONS. REPORT NO. 12. EVALUATION AND SELECTION OF APPLICABLE REACTOR CONCEPTS
1960-01-01

An evaluation of the reactor concepts under consideration for remote military power plants is presented. The concepts include water-cooled and - moderated reactors, both direct and indirect cycle. organic-cooled and -moderated reactors, heavy-water-cooled and -moderated reactors. gas-cooled reactors, sodium- cooled ...

DOE Information Bridge

107
SLAC Model A, B, and C rf loads (Engineering Materials)
1983-01-01

These three drawing lists and the drawings listed thereon provide the information and specifications for constructing the three types of high power rf loads used on the SLAC Linear Accelerator waveguide system. Drawing List DL-767-304-00-R1 Model B rf Load contains the largest number of drawings with Model A and C using some common parts therefrom. Model B load is used in ...

Energy Citations Database

108
NUCLEAR POWER IN CANADA
1960-08-01

Presented at the Conference on Medium and Small Power Reactors, International Atomic Energy Agency, Vienna, September 5-9, 1960. The Canadian program is outlined, and some features of the NPD-2 power reactor are described. Low fueling costs make heavy-water-moderated reactors particularly suitable for ...

Energy Citations Database

109
STUDY OF THE APPLICABILITY OF COMBINING NUCLEAR REACTORS WITH SALINE WATER DISTILLATION PROCESSES. Research and Development Progress Report No. 19
1963-10-31

Activities in a program to select the two optimumcombination saline water reactor-conversion systems for further study and to indicate the direction of further research are reported. Results are presented of an investigation concerning the effects of power level on the cost of steam generated by natural U, heavy water-moderated and -cooled ...

Energy Citations Database

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