UNLIMITED FREE
ACCESS
TO THE WORLD'S BEST IDEAS

SUBMIT
Already a GlobalSpec user? Log in.

This is embarrasing...

An error occurred while processing the form. Please try again in a few minutes.

Customize Your GlobalSpec Experience

Finish!
Privacy Policy

This is embarrasing...

An error occurred while processing the form. Please try again in a few minutes.

ANS - 53.1

Nuclear Safety Design Process For Modular Helium-Cooled Reactor Plants

active, Most Current
Organization: ANS
Publication Date: 1 January 2011
Status: active
Page Count: 135
scope:

This standard applies to the safety design process for plants. This standard provides a process for establishing top-level safety criteria (TLSC); safety functions; top-level design criteria (TLDC); licensing-basis events (LBEs); design-basis accidents (DBAs); safety classification of systems, structures, and components (SSCs); safety analyses; defense-in-depth (DID); and adequate assurance of special treatment requirements for safety-related SSCs throughout the operating life of the plant. This standard does not provide detailed guidance for design; other existing standards cover that.

Plants maintain radioactive releases within public health and safety requirements by passive SSCs and0or inherent characteristics by design. They rely on intrinsic physical characteristics and specific design requirements to do this. While it is beyond the scope of this standard to explain how, the following description of MHR design characteristics provides the basis for this attribute claim. Plants have one or more standard helium-cooled reactor modules, where each module has the following fundamental design characteristics:

• helium primary coolant;

• graphite moderator;

• high integrity, ceramic coated particle nuclear fuel enclosed in a graphite matrix;

• passive decay heat removal capability under extreme undercooling accident conditions;

• defined core geometry that ensures adequate core cooling maintained under all conditions;

• core contained within a metallic reactor pressure vessel (RPV);

• RPV contained within a robust building structure;

• negative temperature coefficient of reactivity.

MHR modules consist of standard nuclear reactor configurations coupled to a direct or indirect power conversion system and0or a process heat utilization system. MHR modules allow replication to produce the required plant output. An MHR direct power conversion system employs a gas turbine in the primary coolant system to convert the thermal energy carried in the primary coolant into electrical energy. An MHR indirect cycle employs an intermediate heat exchanger to transfer thermal energy from the primary coolant to a secondary coolant/working fluid used for power generation. An MHR process heat utilization system employs the thermal energy produced in the reactor core as the energy input to a process for production, such as hydrogen. An MHR module providing process heat may be configured to also cogenerate electricity using either a direct or an indirect cycle.

Document History

January 1, 2011
Nuclear safety design process for modular helium-cooled reactor plants
This standard applies to the safety design process for plants. This standard provides a process for establishing top-level safety criteria (TLSC); safety functions; top-level design criteria (TLDC);...
53.1
January 1, 2011
Nuclear Safety Design Process For Modular Helium-Cooled Reactor Plants
This standard applies to the safety design process for plants. This standard provides a process for establishing top-level safety criteria (TLSC); safety functions; top-level design criteria (TLDC);...
January 1, 2011
nuclear safety design process for modular helium-cooled reactor plants
This standard applies to the safety design process for plants. This standard provides a process for establishing top-level safety criteria (TLSC); safety functions; top-level design criteria (TLDC);...

References

Advertisement