Research on Improved Simplified SCWR Assembly and Core Design

Author:

Lei Yao1,Bangyang Xia1,Di Lu1,Lianjie Wang1

Affiliation:

1. Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, No. 328, Section 1, Changshun Avenue, Shuangliu County, Chengdu 610213, China

Abstract

Abstract A new type of simplified assembly without “water rod” or solid moderator is identified to simplify China Supercritical Water-cooled Reactor with the rated electric power of 1000 MWel (CSR1000) core structure. A study on the properties of this new assembly has been carried out. Under the condition of heat full power, maximum cladding surface temperature (MCST) is 658 °C, very close to safety criterion 650 °C, and maximum linear heat generation rate (MLHGR) is 40.0 kW/m, slightly higher than safety criterion 39 kW/m. Considering rod stuck criterion, the maximum keff is 0.9833, lower than safety criterion 0.99. The discharge burn-up reduced to 21368 MWd/t, a sharp decreasing of 31.1%. This simplified assembly provides a new idea for solving the problem of complex structure of supercritical water-cooled reactor (SCWR).

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference5 articles.

1. Conceptual Design of a High Temperature Power Reactor Cooled and Moderated by Supercritical Light Water;Ann. Nucl. Energy,1998

2. SCWR Transient Safety Analysis Code SCAC-CSR1000;Prog. Nucl. Energy,2015

3. General Design Study on CSR1000 Structure,2013

4. Development of Fuel Management Code Xpack for Supercritical Core;Atom. Energy Sci. Technol.,2015

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