The chapter deals with Verification and Validation (V & V) in nuclear thermal hydraulics. The content of the chapter constitutes: a) a follow-up of Chapter 13 concerned with motivations and features for current V&V; b) a synthesis of advancements in the area of validation and validation procedures, primarily; c) a proposal to promote the role of validation for the improvement of the nuclear thermal hydraulic codes. The chapter includes seven sections in addition to Introduction and Conclusions (i.e. Sections 22.1 and 22.9). Sections 22.2 and 22.3 deal with the connections between requirements / targets for codes (e.g. nuclear reactors safety) and development processes of codes. Noticeably, precision objectives and life cycles of codes are concerned. Best practices for verification and validation constitute the topic of Sections 22.4 and 22.5, respectively; the nodalization qualification is an important aspect discussed in Section 22.4.3. Independent assessment, assessment of validation (or assessment of assessment) together with V & V & C (or V & V plus C = Consistency) constitute key innovative aspects discussed in Sections 22.6 and 22.8. In between those two sections, there is Section 22.7 dealing with code applications; the connection of code applications and code user effect (Section 22.5.8) is stressed together with the need to set-up a code user group to perform a qualified code application, namely for nuclear reactors safety and design. The Technology consistent independent assessment matrix is introduced in Section 22.7.1.2.
Good practices in V&V for system thermal hydraulics codes
D'Auria Francesco
Primo
Writing – Original Draft Preparation
;Bestion D.Secondo
Methodology
;
2024-01-01
Abstract
The chapter deals with Verification and Validation (V & V) in nuclear thermal hydraulics. The content of the chapter constitutes: a) a follow-up of Chapter 13 concerned with motivations and features for current V&V; b) a synthesis of advancements in the area of validation and validation procedures, primarily; c) a proposal to promote the role of validation for the improvement of the nuclear thermal hydraulic codes. The chapter includes seven sections in addition to Introduction and Conclusions (i.e. Sections 22.1 and 22.9). Sections 22.2 and 22.3 deal with the connections between requirements / targets for codes (e.g. nuclear reactors safety) and development processes of codes. Noticeably, precision objectives and life cycles of codes are concerned. Best practices for verification and validation constitute the topic of Sections 22.4 and 22.5, respectively; the nodalization qualification is an important aspect discussed in Section 22.4.3. Independent assessment, assessment of validation (or assessment of assessment) together with V & V & C (or V & V plus C = Consistency) constitute key innovative aspects discussed in Sections 22.6 and 22.8. In between those two sections, there is Section 22.7 dealing with code applications; the connection of code applications and code user effect (Section 22.5.8) is stressed together with the need to set-up a code user group to perform a qualified code application, namely for nuclear reactors safety and design. The Technology consistent independent assessment matrix is introduced in Section 22.7.1.2.I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.
