NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE) (open access)

NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

The Early Program is designed to compute the peak power and total energy release vhich will occur in a reactor due to a step increase of reactivity. These excursions may be terminated by one of several automatic shutoff mechanisms caused by the power excursion itself. The calculation assumes no thermodynanaic delays and assumes void formation is due to heat conduction from the cladding to the moderator. (W.D.M.)
Date: February 26, 1959
Creator: Reiback, E.M. & Stueck, C.J.
System: The UNT Digital Library
THE CRITICAL CURRENT IN THE CASE OF NEUTRAL AND PLASMA BREAKUP (open access)

THE CRITICAL CURRENT IN THE CASE OF NEUTRAL AND PLASMA BREAKUP

An estimate of the critical current for the case of breakup by an arc has been obtained. It is shown that the same technique allows a quick estimate of the critical current in the case of no arc, using neutral and plasma breakup instead. (auth)
Date: February 26, 1959
Creator: Simon, A.
System: The UNT Digital Library
NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE) (open access)

NUCLEAR EXCURSION ANALYSIS ON THE IBM 650 (EARLY CODE)

The early program is designed to compute the peak power and total energy release which will occur in a reactor due to a step increase of reactivity. The calculation assumes no thermodynamic delays and assumes void formation is due to heat conduction from the cladding to the moderator. For periods in the 1 to 10 msec. range, the calculation yields results which are in excellent agreement with SPERT experimental results. (W.D.M.)
Date: February 26, 1959
Creator: Stueck, C.J. & Reiback, E.M.
System: The UNT Digital Library
FOREIGN RESEARCH AND POWER REACTOR PRELIMINARY LIST (open access)

FOREIGN RESEARCH AND POWER REACTOR PRELIMINARY LIST

Foreign research and power reactors are tabulated. Nuclear power buildup goals are given for each nation on which information is available. (J.H.D.)
Date: February 26, 1959
Creator: Ullmann, J.W.
System: The UNT Digital Library