Nuclear design

An analysis shall be provided which shows that the nuclear conditions in 

Basic information on the nuclear design shall include  

The basic information must be supported by reference to the calculation methods and codes, experimental verification of the basic input data, or other information that can support the validity of the nuclear properties, details of which are supplied in this section. 

An analysis shall be provided which shows that the effectiveness, speed of action and shutdown margin of the reactor shutdown system are acceptable and that a single failure in the shutdown system will not prevent the system from completing its safety functions when required. A sufficient shutdown margin shall be provided so that the reactor can be made and maintained subcritical under all operational states and accident conditions. 

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Vitti, J. A. Felton, L. D. Galluzzo, N. G. Otter, J. M. Brittingham, J. C., "Nuclear Design and Economic Comparison of a Conventional and Bullseye LMFBR Core," Nucl. Tech.,... 

This reference neutronics model gives excellent agreement with nuclear design licensing codes, such as the Electricitd de France code COCCINELLE (Version 2.2) [4], and therefore provides a suitable basis for the GPT model that is essential to the computational viability of the optimization process. 

Nakada, T, et al, (2002), Nuclear design of the gas turbine high temperature reactor (GTHTR300). JAERI-Tech 2002-066. 

The International Commission on Radiological Protection (ICRP) recommends specific limits of dose, applicable to stated time intervals (a quarter, a year, and so forth) as guidance for protection of radiation workers these are called maximum permissible doses and are applicable to individuals exposed continuously or intermittently from time to time as their work requires (40). To assist the planning of nuclear designs and operations so as to minimize, appropriately, the low level exposure of members of the public which may ordinarily result from normal operations, dose limits for individual members of the public are recommended by ICRP which are one-tenth or less of the maximum permissible doses for radiation workers. Though these maximum permissible doses and dose limits have little to do directly with the control of major radiation emergencies (i.e., reactor accidents) they are quoted in brief in Table VII. 

Ryazanov, B.G. (1996) Basic Principles and Nuclear Criticality Safety System in Facilities of Nuclear Industry of MINATOM, Russia, Russian-Chinese workshop on nuclear safety in spent nuclear fuel reprocessing, Beijing Nuclear Design Institute, Beijing, May 24-31. 

The Italian criteria for the Unified Nuclear Design (PUN) (ENEA/DISP, 1987) were prepared between 1983-86 for the Italian standardized reactors then being designed. They were accompanied by criteria for severe accidents. 

The CRS was not, however, adopted for the reactor then currently being designed in Italy (a Westinghouse 900 MWe plant chosen for the Unified Nuclear Design, PUN). The adoption of the system would have introduced expense and delay which were considered excessive. In any case, its adoption would have introduced an improvement in a plant already considered satisfactory. 

Michael Wilson and Pat McClure of the Los Alamos National Laboratory s D-5, Nuclear Design and Risk Analysis Group, who are leading the world in risk analysis and also providing key support in and beyond the United States for security and nuclear power safety. 

In the core design of large FBRs, it is essential to improve the prediction accuracy of nuclear characteristics from the viewpoint of both reducing construction cost and insuring plant reliability. Extensive work is being performed in this context to accumulate and evaluate many results of reactor physics experiments in FBR field. As a part of the effort to develop a standard data base for large FBR core nuclear design, the physical consistency of JUPITER experiment and analysis was evaluated by full use of sensitivity analysis, effect of different nuclear data Ubraries and q>pUcation of most-detailed analytical tools. 

The nuclear design calculations for this 1000-MWe fast ceramic reactor used a conservative set of nuclear data. There is experimental evidence to suggest that calculations using these data predict (1) a neutron spectrum that is too hard (quantitative information is given in the paper by Greebler et al. (8) and (2) a positive Doppler contribution from Pu which is too large. 

R. C. DAHLBERG, K. D. LATHROP, and J. C. PEAK, Eds., "Nuclear Design Methods in Use at General Atomic," General Atomic (June 1967). 

S. RAMCHANDRAN and G. H. MADDEN, Analysts of FTR-S Critical Experiments in Support of FTR Nuclear Design, WARD-2171-19, Westinghouse Advanced Reactor Division (April 1971). 

M. H. MERRILL, Nuclear Design Methods and Experimental Data in Use at Gulf General Atomic, Gulf-GA-A12652 (July 1973). 

Brookhaven National Laboratory (BNL). The objectives of this work are (a) to evaluate the cross-section data for U and U in ENOF/B-IV, and (b) to test the validity of specific analytical models used in nuclear design. 

Over the next 20 years however, little advance was made as fxmding worldwide virtually dried up. Many vocal proponents worldwide such as Charles Forsberg and Uri Gat of ORNL and Kazuo Furukawa in Japan at the very least kept interest active during lean times for all nuclear designs (Forsberg, 2006 Furukawa et al., 1990 Furukawa, 1992 Gat, 1992,1997) (Table 7.1). 

RA-8 is a critical facility located at the Pilcaniyeu Technological Complex (Centro Tecnologico de Pilcaniyeu), about 60 km from San Carlos de Bariloche. The reactor, which reached criticality for the first time in June 1997, can be operated during steady state conditions at any constant power up to 10 W, or at 100 W in short transients. The reactor was developed with the specific objective to validate codes used for neutronic core calculations, and to study the nuclear design parameters of a modular Argentinian LWR power reactor named CAREM. 

National and international nuclear design standards that do not include seismic design standards ... 

Special questions of nuclear designing, viz. energy utilization, the problem of pulse thermal loads on the material, etc., are very significant, and can change the requirements of a thermonuclear neutron source. 

The transient response of the reactor system is dependent on the initial power distribution. The nuclear design of the reactor core minimises adverse power distribution through the placement of fuel assemblies and control rods. Power distribution may be characterised by the nuclear enthalpy rise hot chaimel factor (FAH) and the total peaking factor (Fq). 

Reactor physics PNC developed a nuclear design analyds method which consists of nuclear data and reactor constants, calculation models, computer codes and methods for interpolation and extrapolation (Bondarenko-type 26 group constants, computer codes for 2D or 3D diffusion calculations, etc.). In addition, PNC performed a fiill size mockup test (the MOZART project) in the ZEBRA t critical test fa< ty at Winfidth in the UK, and a partial mockup test at the FCA (JAERI) in Japan, to help understand the nuclear characteristics of the Monju core and confirm the validity and accuracy of the nuclear dedgn. 

With the nuclear design referred to in this chapter (further improvement is definitely possible), an availability factor of 95% is quite realistic and for the base load operation mode, the load factor could be 95% as well. 

No requirements for special, sophisticated manufacturing technology the technology for the nuclear design is available in many industrial organizations the technologies for plant systems are widely disseminated. 

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