ERDA Energy Research Abstracts

7310 ( WCAP - 8432 ( Vol.3 ) ) ECCS heat transfer experiences with upper head injection . Volume III . Supplementary information . McIntyre , B.A. ( Westinghouse Electric Corp. , Pittsburgh , Pa . ( USA ) ) . Aug 1976. 75p .

ERDA Energy Research Abstracts


ERDA Energy Research Abstracts

7310 ( WCAP - 8432 ( Vol.3 ) ) ECCS heat transfer experiences with upper head injection . Volume III . Supplementary information . McIntyre , B.A. ( Westinghouse Electric Corp. , Pittsburg ” , Pa . ( USA ) ) . Aug 1976. 75p .

ERDA Energy Research Abstracts


Nuclear Science Abstracts

... ( XN74-25 ( Pev.1 ) ) Analysis of cold leg ECC flow oscillations , 31 : 2504 ( CREARE - TN - 196 ) Combined storage tank and sump for nuclear reactor ( Pat ent ) , 31 : 24960 ECCS heat transfer experiments with upper head injection .

Nuclear Science Abstracts


Blowdown Experiments with Upper Head Injection in G2 17 X 17 Rod Array

SECTION 1 INTRODUCTION 1.1 GENERAL The Upper Head Injection ( UHI ) system , comprising accumulator tanks and a piping ... With this additional core cooling based on experimentally determined heat - transfer relationships , plant ...

Blowdown Experiments with Upper Head Injection in G2 17 X 17 Rod Array


G 2 17x17 Refill Heat Transfer Tests and Analysis

4 . McIntyre , B. A. , and Vijuk , R. P. , " ECCS Heat Transfer Experiments with üpper Head injection , voi . Il , ñeat Transfer Data Analysis and Correlation " , WCAP - 8400 , January , 1975 . 5 . Iloeje , 0.

G 2  17x17 Refill Heat Transfer Tests and Analysis


Design basis Accident Analysis Methods For Light water Nuclear Power Plants

ECCS heat transfer experiments with upper head injection, Volume 1: Test facility, procedures and data, WCAP-8400, Westinghouse Electric Corporation. Cunningham, J. P., Gray, A. D., Mendler, O. J. and Steer, R. W. (1975).

Design basis Accident Analysis Methods For Light water Nuclear Power Plants

This book captures the principles of safety evaluation as practiced in the regulated light-water reactor nuclear industry, as established and stabilized over the last 30 years. It is expected to serve both the current industry and those planning for the future. The work's coverage of the subject matter is the broadest to date, including not only the common topics of modeling and simulation, but also methods supporting the basis for the underlying assumptions, the extension to radiological safety, what to expect in a licensing review, historical perspectives and the implication for new designs.This text is an essential resource for practitioners and students, on the current best-practices in nuclear power plant safety and their basis. Contributors of this work are subject matter experts in their specialties, much of which was nurtured and inspired by Prof. Larry Hochreiter, a prominent nuclear safety pioneer.Related Link(s)

Nuclear Safety

J. P. Cunningham et al . , ECCS Heat Transfer Experiments with Upper Head Injection , Vol . 1 , Test Facility , Procedures , and Data , USAEC Report WCAP - 8432 , Westinghouse Electric Corp. , October 1974 . 94.

Nuclear Safety


Energy Research Abstracts

Final report , 10 : 18405 ( R ; US ) Summary of fuel behavior results from the LOFT experiments , 10 : 18393 ( R ; US ) Water ... US ) COBRA - TF analysis of Westinghouse upper head injection ECCS heat transfer tests , 10 : 18453 ( RA ...

Energy Research Abstracts


Westinghouse Emergency Core Cooling System Evaluation Model Application to Plants Equipped with Upper Head Injection

Wooton , " Penetration of Injected ECC Water Through the Downcomer Annulus in the Presence of Reverse Core Steam Flow " , Battelle Columbus Laboratories , November 1 , 1974 . 4. " ECCS Heat Transfer Experiments with Upper Head Injection ...

Westinghouse Emergency Core Cooling System Evaluation Model Application to Plants Equipped with Upper Head Injection


Post Dryout Heat Transfer

Kelly, J. M. and McIntyre, B. A. (1984) Cobra-TF Analysis of Westinghouse Upper Head Injection ECCS Heat Transfer Tests, Proc. of International Workshop on Fundamentals of Post-Dryout Heat Transfer, Salt Lake City, USA.

Post Dryout Heat Transfer

The study of post-dryout heat transfer has generated great interest because of its importance in determining maximum clad temperature in nuclear reactor loss-of-coolant accidents (LOCAs). An associated phenomenon, the deterioration of heat transfer in boiling, is significant to other industrial sectors. This book provides comprehensive coverage of post-dryout heat transfer, discussing such essential topics as post-dryout heat transfer in dispersed flow, interpretation and use of transient data in surface rewetting by reinstatement of flow or by reducing heat flux, rod bundles, two-phase flow occurrences in the post-dryout region, various methods for predicting ""inverted annular flow,"" and new experiments for measuring thermodynamic nonequilibrium with probes in the channel. The book also presents a basis for independent safety assessment of nuclear reactors and chemical plant systems where post-dryout heat transfer may occur. Post-Dryout Heat Transfer will be a useful reference for researchers and professionals in the nuclear and chemical production industries.

Topical Report Review Status

... FOR 3 - LOOP & 4 - LOOP WITH CORE FLUX PE = 2.32 PROVIDED TECH SPEC INCLUDE ALARMS RI SYM : WCAP - 8400 ( P ) , WCAP - 8432 ( NP ) TITLE : ECCS HEAT TRANSFER EXPERIMENTS WITH UPPER HEAD INJECTION , VOL . I & VOL II .

Topical Report Review Status


INIS Atomindex

INIS Atomindex


Federal Register

Section " I.D.5 deals with head transfer analysis during the refill and reflood phase of a LOCA . ... exemption request is addressed below . plenum injection blockage heat transfer IV . data that is not applicable for the upper Section ...

Federal Register


Public Works for Water and Power Development and Energy Research Appropriation Bill 1978

Specific tests related to ECCS injection into the reactor vessel head area ( the top of the vessel ) are planned in semiscale in fiscal year 1978 . FUEL BEHAVIOR In addition to flow and heat transfer phenomena associated with ECCS ...

Public Works for Water and Power Development and Energy Research Appropriation Bill  1978


Nuclear Power and Its Fuel Cycle Nuclear safety

J. and Steer , R. W. , ECCS Heat Transfer Experiments with Upper Head Injection , Volume 1 Test Facility , Procedures and Data , Westinghouse Nonproprietary Report WCAP - 8432 ( October 1974 ) .

Nuclear Power and Its Fuel Cycle  Nuclear safety


Nuclear Power and Its Fuel Cycle

[ 10 ] Cozzuol , J. M. , Thermal Hydraulic Analysis of the Semiscale Mod - 1 Blowdown Heat Transfer Test Series , ANCR - NUREG ... J. and Steer , R. W. , ECCS Heat Transfer Experiments with Upper Head Injection , Volume 1 Test Facility ...

Nuclear Power and Its Fuel Cycle


Fiscal Year 1978 Budget Review

Alternate ECCS Tests Both the LOFT and Semiscale facilities are designed with the capability to inject emergency core ... Fuel Behavior In addition to flow and heat transfer phenomena associated with ECCS , it is also necessary to ...

Fiscal Year 1978 Budget Review