scholarly journals Fuel utilization improvements in a once-through PWR fuel cycle. Final report on Task 6

1979 ◽  
Author(s):  
D. Dabby

2021 ◽  
Vol 247 ◽  
pp. 01007
Author(s):  
Rodrigo G.G. de Oliveira ◽  
Boris A. Hombourger

Breed-and-burn Molten Salt Reactors are an interesting option of reactor design that allow high fuel utilization while operating on an open fuel cycle. Such reactors usually require specialized codes in order to model its fuel cycle and the flowing fuel in an unmoderated core. In this work, we propose a design and perform a preliminary analysis of a homogeneous chloride salt single-fluid design. The fuel cycle is analyzed using the EQL0D tool in order to model reactor start-up and transition into an equilibrium state. Core simulation is performed using ATARI, an OpenFOAM-based multiphysics code developed at PSI. Results show that the core size for such a reactor is quite big and that it can be easily started with high-assay LEU. In addition, the core has been designed to promote a quasi-1D flow, opening the possibility of modeling the core with legacy codes in the future.



Author(s):  
Alexander N. Chebeskov ◽  
Vladimir I. Oussanov ◽  
Serguei V. Iougai ◽  
Mikhail I. Zavadsky ◽  
Albert Decressin ◽  
...  

Abstract The paper presents some results of system analysis of the plutonium utilization alternatives carried out by Russian specialists with an assistance of their European colleagues in the frames of ISTC#369 and #1443 Projects, financially supported by European Commission states. The multi-attribute utility (MAU) model was chose as the methodology for the analysis. For the time being the work is under continuation, but results of the first stage of the study related to conceptual features of the problem can be summed up and discussed. The study made has shown that effective application of a quantitative model to the problem of plutonium utilization is possible provided that political and technical objectives are strictly defined. A realistic base for the scenarios under consideration is general requirement of a principal importance. The principal result of system consideration is the conclusion that transition from the practice of plutonium accumulation and storing to the strategy of plutonium utilization in nuclear reactors is justified under the real Russian conditions. In an economic sense it is justified by the reason that the expenses of reactor conversion to MOX fuel utilization are comparable with those of long-term storing of plutonium, taking into account modern, and especially future, safety requirements. On the non-proliferation criterion, conversion to MOX fuel utilization is also justified, so as in this case the main source of the proliferation risk — the plutonium store, where plutonium is being stored in the forms being the most attractive for the non-authorized usage — is eliminated. At last, conversion to utilization of stored plutonium results in the decrease of radiation risk for staff and population, as well as in the decrease of impact on the environment due to reduction of some stages of the fuel cycle. Ranking of the plutonium utilization alternatives on a base of account economic, non-proliferation and ecological factors has led to reasonable, explicable results. These results were used in “The concept of the Russian Federation on_disposition of weapons plutonium being released in the course of nuclear disarmament”, which was approved as an official document of Ministry of Atomic Energy of Russian Federation. The main approaches of this strategy were changed significantly when comparing with the previous concept of plutonium utilization. One may expect more detailed recommendations to decision makers in course of further elaboration of scenarios and models at the following stages of the study.



Author(s):  
G. S. You ◽  
W. M. Choung ◽  
J. H. Ku ◽  
S. I. Moon ◽  
H. D. Kim

The Korea Atomic Energy Research Institute (KAERI) has been developing pyroprocess for the dry conditioning of PWR spent nuclear fuels since 1997. The ACPF (Advanced spent fuel Conditioning Process Facility) was developed for volume reduction research on spent PWR fuel. Several years later, the PRIDE (PyRoprocess Integrated inactive Demonstration) facility was also developed for SFR fuel utilization research by pyroprocessing. An integrated full pyroprocess was used in the PRIDE facility. Presently another pyroprocess facility, ESPF (Engineering Scale Pyroprocess Demonstration Facility), is being conceptually designed for the future demonstration of an engineering-scale pyroprocess.





Author(s):  
Akihide Hidaka

Based on the basic policy for introduction of Risk Informed Regulation (RIR) expressed by the Nuclear Safety Commission (NSC) of Japan in 2003, NSC set up the taskforce in April 2004 to take an initiative for coordinated collaboration of related organizations for developing scheme of RIR. Since then the taskforce has reviewed the efforts of related organizations and discussed the issues on further utilization of risk information in Japan. According to the final report prepared by the taskforce in September 2007, the risk consideration in related organizations has made a progress in line mostly with the NSC’s basic policy. For example, the regulatory guide for seismic design was revised in 2006 including combination of deterministic and probabilistic approaches. The regulatory body will start a new inspection system in 2008 that considers the risk informed safety classification of structures, systems and components. However, the followings were identified as important issues in the future: i) promotion of advanced and preliminary trials, ii) comprehensive applications using PSA results for both of the representative and individual plants, iii) preparation of acceptance guidelines for safety and performance goals in risk informed decision making, iv) improvement of PSA quality, v) revision of regulatory guides considering risk information, vi) comprehensive evaluation and promotion by NSC for further utilization of risk information, vii) enhancement of infrastructure such as PSA experts and database, viii) promotion of safety research, ix) application to seismic design, x) Introduction of risk informed approaches into nuclear fuel cycle facilities, and xi) promotion of risk communication, etc.



1978 ◽  
Author(s):  
T.A. Jur ◽  
M.N. Huhns ◽  
D.A. Keating ◽  
D.I. Orloff ◽  
C.A. Rhodes ◽  
...  


2016 ◽  
Author(s):  
Won Sik Yang ◽  
C. S. Lin ◽  
J. S. Hader ◽  
T. K. Park ◽  
P. Deng ◽  
...  
Keyword(s):  


1978 ◽  
Author(s):  
C. Sepsy ◽  
M. McBride ◽  
R. Blancett ◽  
C. Jones




Sign in / Sign up

Export Citation Format

Share Document