A feasibility study on long-life reduced-moderation water reactor with highly protected Pu breeding by doping with minor actinides

2013 ◽  
Vol 54 ◽  
pp. 76-84 ◽  
Author(s):  
Erina Hamase ◽  
Frederic Damian ◽  
Christine Poinot-salanon ◽  
Masaki Saito ◽  
Hiroshi Sagara ◽  
...  
Keyword(s):  
Feasibility Study ◽  
Minor Actinides ◽  
Water Reactor ◽  
Long Life

Safe and Simplified Boiling Water Reactor (SSBWR)

2002 ◽  
Author(s):  
Masaya Ohtsuka ◽  
Koji Fujimura ◽  
Takuji Nagayoshi ◽  
Jun’ichi Yamashita ◽  
Yasuyoshi Kato
Keyword(s):  
Neutron Spectrum ◽  
Nuclear Proliferation ◽  
Boiling Water ◽  
Minor Actinides ◽  
Active Components ◽  
Water Reactor ◽  
Grace Period ◽  
Fuel Assemblies ◽  
Long Life ◽  
High Level

A safe and simplified BWR (SSBWR) has been developed as an innovative future reactor to provide a super-long life core of 20 years and to realize a passive core safety system with infinite grace period. Operability and maintainability can be largely improved by using the super-long life core, cutting the number of active components, and using a one-batch core with no exchange of fuel assemblies, which can also significantly reduce the possibility of nuclear proliferation. Np-237 of MAs (Minor Actinides) can be effectively transmuted using the very hard neutron spectrum of SSBWR and high level radioactive wastes can be reduced.

Minor actinides transmutation on pressurized water reactor burnable poison rods

2017 ◽  
Vol 110 ◽  
pp. 222-229 ◽  
Author(s):  
Wenchao Hu ◽  
Jianping Jing ◽  
Jinsheng Bi ◽  
Chuanqi Zhao ◽  
Bin Liu ◽  
...  
Keyword(s):  
Minor Actinides ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Burnable Poison

A Core Design Study for a Small Modular Boiling Water Reactor with Long-Life Core

2016 ◽  
Vol 193 (3) ◽  
pp. 364-374 ◽  
Author(s):  
Zeyun Wu ◽  
Won Sik Yang ◽  
Shanbin Shi ◽  
Mamoru Ishii
Keyword(s):  
Boiling Water ◽  
Boiling Water Reactor ◽  
Design Study ◽  
Water Reactor ◽  
Long Life

Cyclic Mode of Transmutation of Minor Actinides in Heavy-Water Reactor

2002 ◽  
Author(s):  
Aleksander S. Gerasimov ◽  
Gennady V. Kiselev ◽  
Lidia A. Myrtsymova ◽  
Tamara S. Zaritskaya
Keyword(s):  
Nuclear Fuel ◽  
Heavy Water ◽  
Spent Nuclear Fuel ◽  
Thermal Power ◽  
Minor Actinides ◽  
Water Reactor ◽  
Cyclic Mode ◽  
Equilibrium Mode ◽  
Initial Load ◽  
Heavy Water Reactor

Characteristics of process of transmutation of americium and curium from spent nuclear fuel in heavy-water reactor during first 10 lifetimes and at transition to equilibrium mode are calculated. During transmutation, dangerous nuclides, first of all, 244Cm and 238Pu are accumulated. They cause an increase of radiotoxicity. At first 10 cycles of a transmutation, the radiotoxicity is increased by 11 times in comparison with initial load of transmuted actinides. Heavy-water reactor with thermal power of 1000 MW can transmute americium and curium extracted from 7–8 VVER-1000 type reactors. It means that the required power of transmutation reactor makes about 4% of thermal power of VVER-1000 type reactors.

scholarly journals Neutronic analysis of fuel pin design for the long-life core in a pressurized water reactor

2021 ◽  
Vol 11 (1) ◽  
pp. 9-15
Author(s):  
Van Khanh Hoang ◽  
Vinh Thanh Tran ◽  
Dinh Hung Cao ◽  
Viet Ha Pham Nhu
Keyword(s):  
Coolant Temperature ◽  
Pressurized Water Reactor ◽  
Fuel Temperature ◽  
Pressurized Water ◽  
Water Reactor ◽  
Fuel Model ◽  
Reactivity Coefficients ◽  
Fuel Pin ◽  
Safety Parameters ◽  
Long Life

This work presents the neutronic analysis of fuel design for a long-life core in a pressurized water reactor (PWR). In order to achieve a high burnup, a high enrichment U-235 is traditionally considered without special constraints against proliferation. To counter the excess reactivity, Erbium was selected as a burnable poison due to its good depletion performance. Calculations based on a standard fuel model were carried out for the PWR type core using SRAC code system. A parametric study was performed to quantify the neutronically achievable burnup at a number of enrichment levels and for a numerous geometries covering a wide design space of lattice pitch. The fuel temperature and coolant temperature reactivity coefficients as well as the small and large void reactivity coefficients are also investigated. It was found that it is possible to achieve sufficient criticality up to 100 GWd/tHM burnup without compromising the safety parameters.

scholarly journals Neutronic Analysis of Small Long-Life Pressurized Water Reactor Using (Th-U)O2 Fuels with Gd2O3 and Pa-231 as Burnable Poisons

2020 ◽  
Vol 31 (1) ◽  
pp. 10-15
Author(s):  
Duwi Hariyanto ◽  
Nining Yuningsih ◽  
Sidik Permana
Keyword(s):  
Uranium Dioxide ◽  
Power Plants ◽  
Volume Fraction ◽  
Reactor Core ◽  
Pressurized Water Reactor ◽  
Pressurized Water ◽  
Water Reactor ◽  
Nuclear Data Library ◽  
Long Life ◽  
Enriched Uranium

The requirement for electricity increases with the growth of the human population. The existing power plants have not been able to fulfill all electricity requirements, especially in remote areas. The small long-life pressurized water reactor (PWR) is one of the solutions and innovations in nuclear technology that can produce electrical energy for a long time without refueling. This study aimed to analyze the neutronic of small long-life PWR that using Thorium-Uranium dioxide ((Th-U)O2) fuels with enriched Uranium-235 (U-235) and the addition of Gadolinium (Gd2O3) and Protactinium-231 (Pa-231) as the burnable poisons. The SRAC Code with the JENDL-4.0 nuclear data library had been used for the calculation method. In this study, the geometry of the two-dimensional (R-Z) reactor core with different fuel volume fraction was analyzed. Moreover, variations of the Uranium-235, Gadolinium, and Protactinium-231 fractions in the fuels were carried out. The result in this study was a PWR 420 MWt design using 60% Uranium dioxide fuel with enriched Uranium-235 of 10%-11%-12% and the addition of 0,0125% Gadolinium and 1,0% Protactinium-231 as the burnable poisons that could operate for thirteen years without refueling. The small long-life PWR design could produce a power density of 85,1 watts/cc with the reactivity for less than 4,6% dk/k.

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