Creation of Interface System for Nuclear Reactor Operation

Author(s):  
Yukichi Yamaguchi ◽  
Fumiya Tanabe

Present status of on going JAERI's research project aiming at empirical evaluation of the EID concept is described. The research project is proceeded with three consecutive steps: design and implementation of the interface system, verification, and validation of the interface on a full-scope reactor simulator. Following detailed analysis of system structure in a way of “walking-through” the operation procedure on the simulator, a new interface system was created on this. In the newly created interface system, sets of graphical display formats representing higher levels of information items and new navigation mechanism were introduced to cope with complex nature of reactor system. At present, verification work for this new interface system is being conducted.

JOM ◽  
2009 ◽  
Vol 61 (7) ◽  
pp. 24-27
Author(s):  
R. Szilard ◽  
P. Planchon ◽  
J. Busby

2018 ◽  
Vol 2018 ◽  
pp. 1-9 ◽  
Author(s):  
Sónia Dias ◽  
Ana Gama ◽  
Daniel Simões ◽  
Luís Mendão

A participatory HIV research project was conducted with sex workers (SW) and men who have sex with men (MSM) to understand epidemiological HIV dynamics and associated sociobehavioural factors among these vulnerable groups. We examine the impact of this project, critically analysing the processes undertaken and focusing on the advantages and the challenges faced. A partnership was built through two Community Advisory Boards (CABs) and a Scientific Commission (SC). Regular meetings, workshops, and focus groups were conducted with CABs, SC, and partners to assess the processes and outcomes of the project implementation. This participatory research produced change processes with impacts at different levels: individuals, community organizations, health professionals, academics, and policy-makers. Advantages of the participatory process were encountered but also challenges, evidencing the dynamic and complex nature of each project’s stage. This project showed that participatory research can work as an intervention. Indeed, it triggered a dynamic and interactive process of knowledge coproduction and translation into effective community-oriented health actions and policies. The participatory research reproduced an innovative alliance for HIV prevention and sexual health promotion responsive to local needs and priorities. Further efforts are needed to systematize and evaluate the processes and impacts of participatory health research.


Author(s):  
Satoshi Hanada ◽  
Koji Ito ◽  
Kenji Mashio

The US-APWR, currently under Design Certification review by the U.S. Nuclear Regulatory Commission, is a four loop evolutionary pressurized water reactor with a four train active safety system applied by Mitsubishi Heavy Industries. The digital Instrumentation and Control (I&C) System and Human Systems Interface (HSI) system are to be applied to the US-APWR. This design is currently being applied to the latest Japanese PWR plant and to nuclear power plant I&C modernization program in Japan. The US-APWR digital I&C and HSI system (HSIS) utilizes computerized systems, including computer-based procedures and alarm prioritization, relying principally on an HSIS with soft controls, console based visual display units (VDUs) and a large, heads up, overview display panel. Conventional hard-wired controls are limited to system level manual actions and a Diverse Actuation System (DAS). The overall design philosophy of the US-APWR is based on the concept that operator performance will be enhanced through the integration of safety and non-safety display and control systems in a robust digital environment. This philosophy is augmented, for diversity, by the application of independent safety soft displays and controls. In addition, non-digital diverse automatic and manual actuation system is introduced. As with all the advanced designs, the digital systems open as many questions as they answer. To address these new questions, for an eight week period during the months of July and August 2008, an extensive verification and validation (V&V) program was completed with the objective of assessing US operators’ performance in this digital design environment. (Robert E. Hall et al., 2008, “US-APWR Human Systems Interface System V&V Results: Impact on Digital I&C Design”, 17th International Conference on Nuclear Engineering, ICONE17-75176) [1] Over this time period, U.S. operating crews were subjected to exercise in Mitsubishi dynamic simulator. To follow up above mentioned V&V activities, additional test during the months of this spring in 2009 has been carried out to resolve human engineering discrepancies (HEDs) induced from the previous evaluation and the participants’ comments and performance. Subjective and objective data were collected on each crew for each scenario and an extensive convergent measures analysis was performed, resulting in the identification of both specific design as well as generic conclusions. This paper discusses the digital HSIS of the US-APWR design, the V&V program data collection and analysis, and the study results related to the ongoing discussion of the impacts of digital systems on human performance, such as workload, navigation, situation awareness, operator training and licensing.


Author(s):  
Jian Zhang ◽  
Hong Yu ◽  
Zhi Gang ◽  
Keyuan Zhou ◽  
Yun Hu ◽  
...  

Traveling wave reactor is a kind of nuclear reactor that can convert fertile material into fissile fuel as it runs using the process of nuclear transmutation. In the ignition stage of traveling wave reactor, the core performance is especially complex, since the fissile fuel and fertile material is put in different regions at the beginning. And the distribution of power density will change severely with burn-up during the reactor operation. It is an important part of the traveling wave reactor study to optimize the design of the ignition stage. In this paper, based on a two-dimensional RZ geometry model, some schemes with different sizes and compositions of the ignition zone, middle ignition zone position design and burnable neutron poison addition are simulated and analyzed. Finally, an optimized core design with multi-zone configuration and burnable neutron poison addition is shown. Some design outlines are introduced for further study.


2019 ◽  
Author(s):  
Katherine Mitchell ◽  
Hunter Horner ◽  
Alex Resnick ◽  
Jungkyu Park ◽  
Eduardo B. Farfán ◽  
...  

Abstract Molecular displacement occurs in the oxide fuels of nuclear reactors during operation. This causes several types of point defects to be generated inside the oxide nuclear fuels. To improve the safety and efficiency of nuclear reactor operation, it is necessary to better understand the effects of point defects on the properties of the oxide fuels. In this study, we examine the effects of interstitial defects on thermal transport in two representative actinide oxides used in modern reactors (UO2, and PuO2). Reverse non-equilibrium molecular dynamics (RNEMD) is employed to approximate the thermal conductivities for the aforementioned fuels at several sample lengths and at defect concentrations of 0.1%, 1%, and 5%. The results show that alterations to the lattice structures of these fuels reduce their thermal conductivities significantly. For example, oxygen interstitial defects at concentrations even as low as 0.1% decreased thermal conductivity by 20% at 100 units for each fuel.


Author(s):  
K. R. Kim ◽  
S. D. Kim ◽  
Y. M. Song

Recently the development of graphical methods using the ISAAC code’s calculation data has been started in order to show the Wolsong 1 & 2 PHWR plants behaviour during the severe accidents. This graphic model is designed to provide two basic functions: one is to provide the graphical display of several plants systems together with the important parameters. For example, the representative T/H behaviour, fuel behaviour, fuel channel behaviour, reactor core behaviour, containment behaviour and fission product behaviour are going to be displayed in a graphic window. The other function is the control capability equipped with the controllable valves and pumps in the PHWR SAMG. In this paper, details of the elementary technical aspects of the ISAAC graphic model are presented which are the system structure, ISAAC variable definition, data communication methods and graphical display generation.


2013 ◽  
Vol 2 (1) ◽  
pp. 113-118 ◽  
Author(s):  
S. Yue ◽  
S. Polugari ◽  
V. Anghel ◽  
J. Hilborn ◽  
B. Sur

SLOWPOKE-2 (LEU core) is a pool-type nuclear reactor with a maximum nominal thermal power of 20 kW. It uses a pelletized uranium oxide fuel (19.9% enrichment) and provides a useful high neutron flux in the order of 1012 n.cm2s-1. The key safety features built into the reactor design are the strictly limited amount of excess reactivity and the negative reactivity feedback characteristics, which provide a demonstrably safe self-limiting power excursion response to large reactivity insertions. However, the limited amount of excess reactivity also limits continuous prolonged reactor operation at full power. With a 4 mk excess reactivity, the reactor can operate for about one day at full power, 20 kW, before criticality is lost due to temperature effects and xenon poisoning. A new safety concept is proposed in this paper that enables the continuous operation to a few months by increasing the excess reactivity from 4 mk to 8 mk. A Matlab/simulink model of SLOWPOKE-2 has demonstrated that core operation life can be extended to several months without adding a beryllium shim.


Nature ◽  
1966 ◽  
Vol 209 (5018) ◽  
pp. 64-64 ◽  
Author(s):  
DONALD G. CARPENTER ◽  
RICHARD E. DENFELD ◽  
KENNETH H. KRONLUND

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