SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary PDF Download

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SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary PDF Author:
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Languages : en
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SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 1: Summary PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 3: Surry Unit 1 Cycle 2

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 3: Surry Unit 1 Cycle 2 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 4: Three Mile Island Unit 1 Cycle 5

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 4: Three Mile Island Unit 1 Cycle 5 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

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Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5, North Anna Unit 1 Cycle 5

Scale-4 Analysis of Pressurized Water Reactor Critical Configurations: Volume 5, North Anna Unit 1 Cycle 5 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description
ANSI/ANS 8.1 requires that calculational methods for away-from- reactor (AFR) criticality safety analyses be validated against experiment. This report summarizes part of the ongoing effort to benchmark AFR criticality analysis methods using selected critical configurations from commercial PWRs. Codes and data in the SCALE-4 code system were used. This volume documents the SCALE system analysis of one reactor critical configuration for North Anna Unit 1 Cycle 5. The KENO V.a criticality calculations for the North Anna 1 Cycle 5 beginning-of-cycle model yielded a value for k[sub eff] of 1. 0040[+-]0.0005.

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 2: Sequoyah Unit 2 Cycle 3

SCALE-4 Analysis of Pressurized Water Reactor Critical Configurations. Volume 2: Sequoyah Unit 2 Cycle 3 PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages :

Book Description


Radioactive Waste Management

Radioactive Waste Management PDF Author:
Publisher:
ISBN:
Category :
Languages : en
Pages : 388

Book Description


Government Reports Announcements & Index

Government Reports Announcements & Index PDF Author:
Publisher:
ISBN:
Category : Science
Languages : en
Pages : 778

Book Description


Structural Alloys for Nuclear Energy Applications

Structural Alloys for Nuclear Energy Applications PDF Author: Robert Odette
Publisher: Newnes
ISBN: 012397349X
Category : Technology & Engineering
Languages : en
Pages : 673

Book Description
High-performance alloys that can withstand operation in hazardous nuclear environments are critical to presentday in-service reactor support and maintenance and are foundational for reactor concepts of the future. With commercial nuclear energy vendors and operators facing the retirement of staff during the coming decades, much of the scholarly knowledge of nuclear materials pursuant to appropriate, impactful, and safe usage is at risk. Led by the multi-award winning editorial team of G. Robert Odette (UCSB) and Steven J. Zinkle (UTK/ORNL) and with contributions from leaders of each alloy discipline, Structural Alloys for Nuclear Energy Applications aids the next generation of researchers and industry staff developing and maintaining steels, nickel-base alloys, zirconium alloys, and other structural alloys in nuclear energy applications. This authoritative reference is a critical acquisition for institutions and individuals seeking state-of-the-art knowledge aided by the editors’ unique personal insight from decades of frontline research, engineering and management. Focuses on in-service irradiation, thermal, mechanical, and chemical performance capabilities. Covers the use of steels and other structural alloys in current fission technology, leading edge Generation-IV fission reactors, and future fusion power reactors. Provides a critical and comprehensive review of the state-of-the-art experimental knowledge base of reactor materials, for applications ranging from engineering safety and lifetime assessments to supporting the development of advanced computational models.

Energy Research Abstracts

Energy Research Abstracts PDF Author:
Publisher:
ISBN:
Category : Power resources
Languages : en
Pages : 782

Book Description


Transactions of the American Nuclear Society

Transactions of the American Nuclear Society PDF Author: American Nuclear Society
Publisher:
ISBN:
Category : Nuclear engineering
Languages : en
Pages : 596

Book Description