Published October 1991 | Version v1
Miscellaneous

Verification tests performed in APWR development program

Creators

  • 1. Mitsubishi Heavy Industries, Ltd., Tokyo (Japan)

Description

The APWR has been developed as a nuclear plant incorporated major improvements in areas such as safety, reliability, operational performance and economy. During development of the APWR, various designs, tests and evaluations were conducted according to an elaborately planned development program. The adequacy and reliability of major equipment were confirmed by extensive testing from the design phase to the final verification stage, those were, about 60 of design tests and 14 of verification tests. Especially, the Nuclear Power Engineering Test Center(NUPEC) was commissioned by the Ministry of International Trade and Industry(MITI), to confirm the reliability of the core internals, fuel assembly and core components by tests called 'Hydraulic Flow Test of APWR FUEL under Simulated Operating Conditions' and 'Verification Test of Upper Core Internals for APWR'. This report is to present the role of the tests in the APWR development and to introduce the outline of major verification tests

Part of:
The 13th KAIF-JAIF Seminar on Nuclear Industry

Additional details

Publishing Information

Publisher
Korea Atomic Industrial Forum, Inc.
Imprint Place
Seoul (Korea, Republic of)
Imprint Title
The 13th KAIF-JAIF Seminar on Nuclear Industry
Imprint Pagination
395 p.
Journal Page Range
p. 311-334

Conference

Title
The 13th KAIF-JAIF Seminar on Nuclear Industry
Dates
28-30 Oct 1991
Place
Seoul (Korea, Republic of)

INIS

Country of Publication
Korea, Republic of
Country of Input or Organization
Korea, Republic of
INIS RN
38075291
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Resource subtype / Literary indicator
Conference, Non-conventional Literature
Descriptors DEI
FUEL ASSEMBLIES; PWR TYPE REACTORS; RELIABILITY; SAFETY; STEAM GENERATORS; VERIFICATION
Descriptors DEC
BOILERS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTORS; THERMAL REACTORS; VAPOR GENERATORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Notes
17 figs, 1 tab