Proposals for the construction of space systems based on small spacecraft and a transport and power module with a nuclear power plant

2016 ◽  
Vol 50 (7) ◽  
pp. 471-476 ◽  
Author(s):  
A. A. Barabanov ◽  
B. P. Papchenko ◽  
K. M. Pichkhadze ◽  
S. G. Rebrov ◽  
A. V. Semenkin ◽  
...  
Author(s):  
Gary P. McGee ◽  
Steven M. Unikewicz

The American Society of Mechanical Engineers (ASME) Operation and Maintenance of Nuclear Power Plants, Division 1, “OM Code: Section IST,” defines a post-2000 plant as a nuclear power plant that was issued (or will be issued) its construction permit, or combined license for construction and operation, by the applicable regulatory authority on or following January 1, 2000. The NuScale advanced small modular reactor plant is passive, pressurize water reactor, designed such that from one (1) to twelve (12) nuclear power plant modules (NPM) can operate within a single Reactor Building. Each NuScale Power Module (NPM) consist of a reactor core, two steam generator tube bundles, and a pressurizer contained within a single reactor vessel, along with the containment vessel that immediately surrounds the reactor vessel and is rated at 160 MWt. The ASME Operation and Maintenance (OM) Code was written considering single-unit reactor plants, not multi-modular SMRs. The ASME Sub-Committee, New Reactors is developing a new Sub-Section, ISTG to address inservice testing (IST) of valves for all new and advanced reactor types. This paper reviews the unique aspects and programmatic solutions for preservice testing (PST) and IST specific to the NuScale small modular reactor (SMR). The functional design, qualification provisions and IST program is described. The PST and preservice test period will be discussed as some preservice testing may be completed in the factory prior to shipping the reactor module to the site. Additionally, methods eliminate overlap, redundancy and excessive testing between the preservice testing (PST) and IST program plans will be explored. The intent of these solutions is to provide reasonable assurance that the ASME BPV Code, Section III Class 1, Class 2, Class 3, non-safety-related and non-ASME valves that have an important function will operate when needed. The program considers both deterministic and risk insights in its evaluation of PST and IST and meets the requirements of the ASME OM Code as endorsed by 10 CFR 50.55a. Paper published with permission.


2020 ◽  
Vol 39 (5) ◽  
pp. 6339-6350
Author(s):  
Esra Çakır ◽  
Ziya Ulukan

Due to the increase in energy demand, many countries suffer from energy poverty because of insufficient and expensive energy supply. Plans to use alternative power like nuclear power for electricity generation are being revived among developing countries. Decisions for installation of power plants need to be based on careful assessment of future energy supply and demand, economic and financial implications and requirements for technology transfer. Since the problem involves many vague parameters, a fuzzy model should be an appropriate approach for dealing with this problem. This study develops a Fuzzy Multi-Objective Linear Programming (FMOLP) model for solving the nuclear power plant installation problem in fuzzy environment. FMOLP approach is recommended for cases where the objective functions are imprecise and can only be stated within a certain threshold level. The proposed model attempts to minimize total duration time, total cost and maximize the total crash time of the installation project. By using FMOLP, the weighted additive technique can also be applied in order to transform the model into Fuzzy Multiple Weighted-Objective Linear Programming (FMWOLP) to control the objective values such that all decision makers target on each criterion can be met. The optimum solution with the achievement level for both of the models (FMOLP and FMWOLP) are compared with each other. FMWOLP results in better performance as the overall degree of satisfaction depends on the weight given to the objective functions. A numerical example demonstrates the feasibility of applying the proposed models to nuclear power plant installation problem.


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