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2017 | OriginalPaper | Buchkapitel

4. Policy of Safety Assurance (Design Constraints and Additional Functional Requirements)

verfasst von : Yoshio Kani

Erschienen in: Fast Reactor System Design

Verlag: Springer Singapore

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Abstract

This chapter discusses the assurance of safety, which is particularly important for nuclear power plants. This becomes a design constraint and requires additional functions. This chapter first presents an overview of the basics of safety assurance for all nuclear reactors and then discusses the characteristics of the FR and the basic policies for assuring safety. It specifically describes the handling of core fuel possessing nuclear characteristics differing from that used in light-water reactors, safety measures for plants using sodium, and severe accident measures.

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Fußnoten
1
“IP” is the early phase of a core damage and meltdown process, where the wrapper tube of each fuel assembly maintains the essential integrity and molten core materials move only in the axial direction within the wrapper tubes. When the “IP” does not lead to significant power rise due to prompt criticality, gradual melting of wrapper tubes subsequently causes the mutual movement of molten core materials among fuel assemblies, eventually resulting in a condition where the reactivity changes due to the whole core motion. The subsequent process is referred to as “TP.”
 
Literatur
1.
Zurück zum Zitat Fundamental Safety Principles. IAEA Safety Standard (2006) Fundamental Safety Principles. IAEA Safety Standard (2006)
2.
Zurück zum Zitat Major matters discussed on the safety goal before the previous Commission Meeting. (April 3, 2013) (in Japanese), Document prepared for the 2nd NRA (Nuclear Regulation Authority) Commission meeting (April 10, 2013) Major matters discussed on the safety goal before the previous Commission Meeting. (April 3, 2013) (in Japanese), Document prepared for the 2nd NRA (Nuclear Regulation Authority) Commission meeting (April 10, 2013)
3.
Zurück zum Zitat Basic Safety Principles for Nuclear Power Plants. 75-INSAG-3 Rev.1, INSAG-12, IAEA (1999) Basic Safety Principles for Nuclear Power Plants. 75-INSAG-3 Rev.1, INSAG-12, IAEA (1999)
4.
Zurück zum Zitat Rules for the criteria of location, structure and equipment of commercialized power reactors and associated facilities (in Japanese), Nuclear Regulation Authority (2013) Rules for the criteria of location, structure and equipment of commercialized power reactors and associated facilities (in Japanese), Nuclear Regulation Authority (2013)
5.
Zurück zum Zitat Safety of Nuclear Power Plants: Design. IAEA Requirements No. SSR2/1 (2012) Safety of Nuclear Power Plants: Design. IAEA Requirements No. SSR2/1 (2012)
6.
Zurück zum Zitat Safety Objectives for New Power Reactors. WENRA (Western European Nuclear Regulator’s Association) (2009) Safety Objectives for New Power Reactors. WENRA (Western European Nuclear Regulator’s Association) (2009)
7.
Zurück zum Zitat R. Nakai, Design and Assessment Approach on Advanced SFR Safety with Emphasis on Core Disruptive Accident Issue, Proceedings of international conference on fast reactors and related fuel cycles: Challenges and opportunities FR09, Kyoto, Japan, December 7–11 (2009) R. Nakai, Design and Assessment Approach on Advanced SFR Safety with Emphasis on Core Disruptive Accident Issue, Proceedings of international conference on fast reactors and related fuel cycles: Challenges and opportunities FR09, Kyoto, Japan, December 7–11 (2009)
8.
Zurück zum Zitat Safety Evaluation Policy for Fast Breeder Reactors (FBRs). Regulatory Guide of the former Nuclear Safety Commission (1980) Safety Evaluation Policy for Fast Breeder Reactors (FBRs). Regulatory Guide of the former Nuclear Safety Commission (1980)
9.
Zurück zum Zitat Application Document for Reactor Establishment License of Prototype Fast Breeder Reactor Monju (in Japanese) (1980) Application Document for Reactor Establishment License of Prototype Fast Breeder Reactor Monju (in Japanese) (1980)
10.
Zurück zum Zitat H. Yamano, S. Kubo, Y. Shimakawa, K. Fujita, T. Suzuki, K. Kurisaka, Conceptual Design for a Large-Scale Japan Sodium-Cooled Fast Reactor (2) Safety Design and Evaluation in JSFR. Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, France (May 2–5, 2011) No.11219 H. Yamano, S. Kubo, Y. Shimakawa, K. Fujita, T. Suzuki, K. Kurisaka, Conceptual Design for a Large-Scale Japan Sodium-Cooled Fast Reactor (2) Safety Design and Evaluation in JSFR. Proceedings of 2011 International Congress on Advances in Nuclear Power Plants (ICAPP 2011), Nice, France (May 2–5, 2011) No.11219
11.
Zurück zum Zitat Document prepared for the 2nd investigation committee meeting on Monju comprehensive safety evaluation (in Japanese), Japan Atomic Energy Agency (JAEA) (2011) Document prepared for the 2nd investigation committee meeting on Monju comprehensive safety evaluation (in Japanese), Japan Atomic Energy Agency (JAEA) (2011)
12.
Zurück zum Zitat Investigative Study on Safety Design Criteria of Generation-IV Sodium-cooled Fast Reactor (fiscal year 2012) (in Japanese), Special Expert Committee of Atomic Energy Society of Japan (AESJ) (2013) Investigative Study on Safety Design Criteria of Generation-IV Sodium-cooled Fast Reactor (fiscal year 2012) (in Japanese), Special Expert Committee of Atomic Energy Society of Japan (AESJ) (2013)
13.
Zurück zum Zitat I. Sato, et al., Elimination of severe recriticality events in the Core Disruptive Accident of JSFR aiming at In-Vessel Retention of the core materials, Proceedings of international conference on fast reactors and related fuel cycles: Challenges and opportunities FR09, Kyoto, Japan, December 7–11 (2009) I. Sato, et al., Elimination of severe recriticality events in the Core Disruptive Accident of JSFR aiming at In-Vessel Retention of the core materials, Proceedings of international conference on fast reactors and related fuel cycles: Challenges and opportunities FR09, Kyoto, Japan, December 7–11 (2009)
Metadaten
Titel
Policy of Safety Assurance (Design Constraints and Additional Functional Requirements)
verfasst von
Yoshio Kani
Copyright-Jahr
2017
Verlag
Springer Singapore
DOI
https://doi.org/10.1007/978-981-10-2821-2_4