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Title: Heavy water moderated power reactors. Progress Report for February 1960

Abstract

At the end of February 1960, 30% of the construction of the Heavy Water Components Test Reactor (HWCTR) was compplete. Limits for safe operation of the reactor were defined, and the general procedures for startup, shutdown, and normal operation here formulated. A detailed analysis of operating stresses in the reactor vessel defined the ling that can be tolerated. Core swelling produced a maximum cladding strain of 0.7% in a Zircaloy-2-clad tube of U-2 wt.% Zr that was irradiated to an average burnup of 1100 Mwd/t in the VBWR. (For preceding period see DP-465.) (auth)

Authors:
;  [1]
  1. comps.
Publication Date:
Research Org.:
Du Pont de Nemours (E.I.) & Co. Atomic Energy Div., Wilmington, DE (United States); Savannah River National Lab (SRNL), Aiken, SC (United States)
Sponsoring Org.:
US Atomic Energy Commission (AEC)
OSTI Identifier:
4182186
Report Number(s):
DP-475
NSA Number:
NSA-14-016442
DOE Contract Number:  
AT(07-2)-1
Resource Type:
Technical Report
Country of Publication:
United States
Language:
English
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; BURNUP; COOLING; DEFORMATION; FUEL CANS; FUEL ELEMENTS; HEATING; HEAVY WATER MODERATOR; HWCTR; IRRADIATION; OPERATION; PLANNING; POWER PLANTS; PRESSURE VESSELS; REACTOR SAFETY; REACTORS; SHUTDOWN; STANDARDS; STARTUP; THERMAL STRESSES; TUBES; ZIRCALOY

Citation Formats

Hood, R. R., and Isakoff, L. Heavy water moderated power reactors. Progress Report for February 1960. United States: N. p., 1960. Web. doi:10.2172/4182186.
Hood, R. R., & Isakoff, L. Heavy water moderated power reactors. Progress Report for February 1960. United States. doi:10.2172/4182186.
Hood, R. R., and Isakoff, L. Fri . "Heavy water moderated power reactors. Progress Report for February 1960". United States. doi:10.2172/4182186. https://www.osti.gov/servlets/purl/4182186.
@article{osti_4182186,
title = {Heavy water moderated power reactors. Progress Report for February 1960},
author = {Hood, R. R. and Isakoff, L.},
abstractNote = {At the end of February 1960, 30% of the construction of the Heavy Water Components Test Reactor (HWCTR) was compplete. Limits for safe operation of the reactor were defined, and the general procedures for startup, shutdown, and normal operation here formulated. A detailed analysis of operating stresses in the reactor vessel defined the ling that can be tolerated. Core swelling produced a maximum cladding strain of 0.7% in a Zircaloy-2-clad tube of U-2 wt.% Zr that was irradiated to an average burnup of 1100 Mwd/t in the VBWR. (For preceding period see DP-465.) (auth)},
doi = {10.2172/4182186},
journal = {},
number = ,
volume = ,
place = {United States},
year = {1960},
month = {4}
}